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Sample records for evaluated nuclear data file

  1. Benchmark comparisons of evaluated nuclear data files

    International Nuclear Information System (INIS)

    Resler, D.A.; Howerton, R.J.; White, R.M.

    1994-05-01

    With the availability and maturity of several evaluated nuclear data files, it is timely to compare the results of integral tests with calculations using these different files. We discuss here our progress in making integral benchmark tests of the following nuclear data files: ENDL-94, ENDF/B-V and -VI, JENDL-3, JEF-2, and BROND-2. The methods used to process these evaluated libraries in a consistent way into applications files for use in Monte Carlo calculations is presented. Using these libraries, we are calculating and comparing to experiment k eff for 68 fast critical assemblies of 233,235 U and 239 Pu with reflectors of various material and thickness

  2. ENSDF: The evaluated nuclear structure data file

    International Nuclear Information System (INIS)

    Martin, M.J.

    1986-01-01

    The structure, organization, and contents of the Evaluated Nuclear Structure Data File, ENSDF, will be discussed. This file summarizes the state of experimental nuclear structure data for all nuclei as determined from consideration of measurements reported world wide. Special emphasis will be given to the data evaluation procedures and consistency checks utilized at the input stage and to the retrieval capabilities of the system at the output stage

  3. Evaluated nuclear data file of Th-232

    International Nuclear Information System (INIS)

    Meadows, J.; Poenitz, W.; Smith, A.; Smith, D.; Whalen, J.; Howerton, R.

    1977-09-01

    An evaluated nuclear data file for thorium is described. The file extends over the energy range 0.049 (i.e., the inelastic-scattering threshold) to 20.0 MeV and is formulated within the framework of the ENDF system. The input data base, the evaluation procedures and judgments, and ancillary experiments carried out in conjunction with the evaluation are outlined. The file includes: neutron total cross sections, neutron scattering processes, neutron radiative capture cross sections, fission cross sections, (n;2n) and (n;3n) processes, fission properties (e.g., nu-bar and delayed neutron emission) and photon production processes. Regions of uncertainty are pointed out particularly where new measured results would be of value. The file is extended to thermal energies using previously reported resonance evaluations thereby providing a complete file for neutronic calculations. Integral data tests indicated that the file was suitable for neutronic calculations in the MeV range

  4. Evaluated nuclear-data file for niobium

    International Nuclear Information System (INIS)

    Smith, A.B.; Smith, D.L.; Howerton, R.J.

    1985-03-01

    A comprehensive evaluated nuclear-data file for elemental niobium is provided in the ENDF/B format. This file, extending over the energy range 10 -11 -20 MeV, is suitable for comprehensive neutronic calculations, particulary those dealing with fusion-energy systems. It also provides dosimetry information. Attention is given to the internal consistancy of the file, energy balance, and the quantitative specification of uncertainties. Comparisons are made with experimental data and previous evaluated files. The results of integral tests are described and remaining outstanding problem areas are cited. 107 refs

  5. Evaluated Nuclear Structure Data File (ENSDF)

    International Nuclear Information System (INIS)

    Bhat, M.R.

    1991-01-01

    The Evaluated Nuclear Structure Data File (ENSDF), is maintained by the National Nuclear Data Center (NNDC) on behalf of the international Nuclear Structure and Decay Data (NSDD) network organized under the auspices of the International Atomic Energy Agency. ENSDF provides evaluated experimental nuclear structure and decay data for basic and applied research. The activities of the NSDD network, the publication of the evaluations, and their use in different applications are described. Since 1986, the ENSDF and related numeric and bibliographic data bases have been made available for on-line access. The current status of these data bases, and future plans to improve the on-line access to their contents are discussed. 8 refs., 4 tabs

  6. Status of the evaluated nuclear structure data file

    International Nuclear Information System (INIS)

    Martin, M.J.

    1991-01-01

    The structure, organization, and contents of the Evaluated Nuclear Structure Data File (ENSDF) are discussed in this paper. This file contains a summary of the state of experimental nuclear structure data for all nuclides as determined from consideration of measurements reported worldwide in the literature. Special emphasis is given to the data evaluation procedures, the consistency checks, and the quality control utilized at the input stage and to the retrieval capabilities of the system at the output stage. Recent enhancements of the on-line interaction with the file contents is addressed as well as procedural changes that will improve the currency of the file

  7. The evaluated nuclear structure data file: Philosophy, content, and uses

    International Nuclear Information System (INIS)

    Burrows, T.W.

    1990-01-01

    The Evaulated Nuclear Structure Data File (ENSDF) is maintained by the National Nuclear Data Center (NNDC) on behalf of the international Nuclear Structure and Decay Data Network sponsored by the International Atomic Energy Agency, Vienna. Data for A=5 to 44 are extracted from the evaluations published in Nuclear Physics; for A≥45 the file is used to produce the Nuclear Data Sheets. The philosophy and methodology of ENSDF evaluations are outlined, along with the file contents of relevance to radionuclide metrologists; the service available at various nuclear data centers and the NNDC on-line capabilities are also discussed. Application codes have been developed for use with ENSDF, and the program RADLST is used as an example. The interaction of ENSDF evaluation with other evaluations is also discussed. (orig.)

  8. Titanium-II: an evaluated nuclear data file

    International Nuclear Information System (INIS)

    Philis, C.; Howerton, R.; Smith, A.B.

    1977-06-01

    A comprehensive evaluated nuclear data file for elemental titanium is outlined including definition of the data base, the evaluation procedures and judgments, and the final evaluated results. The file describes all significant neutron-induced reactions with elemental titanium and the associated photon-production processes to incident neutron energies of 20.0 MeV. In addition, isotopic-reaction files, consistent with the elemental file, are separately defined for those processes which are important to applied considerations of material-damage and neutron-dosimetry. The file is formulated in the ENDF format. This report formally documents the evaluation and, together with the numerical file, is submitted for consideration as a part of the ENDF/B-V evaluated file system. 20 figures, 9 tables

  9. Evaluated nuclear data file ENDF/B-VI

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1991-01-01

    For the past 25 years, the United States Department of Energy has sponsored a cooperative program among its laboratories, contractors and university research programs to produce an evaluated nuclear data library which would be application independent and universally accepted. The product of this cooperative activity is the ENDF/B evaluated nuclear data file. After approximately eight years of development, a new version of the data file, ENDF/B-VI has been released. The essential features of this evaluated data library are described in this paper. 7 refs

  10. Procedures manual for the Evaluated Nuclear Structure Data File

    International Nuclear Information System (INIS)

    Bhat, M.R.

    1987-10-01

    This manual is a collection of various notes, memoranda and instructions on procedures for the evaluation of data in the Evaluated Nuclear Structure Data File (ENSDF). They were distributed at different times over the past few years to the evaluators of nuclear structure data and some of them were not readily avaialble. Hence, they have been collected in this manual for ease of reference by the evaluators of the international Nuclear Structure and Decay Data (NSDD) network contribute mass-chains to the ENSDF. Some new articles were written specifically for this manual and others are reivsions of earlier versions

  11. Status of transactinium nuclear data in the evaluated nuclear structure data file

    International Nuclear Information System (INIS)

    Ewbank, W.B.

    1980-01-01

    The structure and organization of the Evaluated Nuclear Structure Data File (ENSDF) which serves as the source data base for the production of drawings and tables for the ''Nuclear Data Sheets'' journal is described. The updating and output features of ENSDF are described with emphasis on nuclear structure and decay data of the transactinium isotopes. (author)

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

    International Nuclear Information System (INIS)

    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 ≤ 293), the Evaluated Nuclear Structure Data File (ENSDF) contains evaluated structure information. For masses 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

  13. Status of transactinium nuclear data in the Evaluated Nuclear Structure Data File

    International Nuclear Information System (INIS)

    Ewbank, W.B.

    1979-01-01

    The organization and program of the Nuclear Data Project are described. An Evaluated Nuclear Structure Data File (ENSDF) was designed to contain most of the data of nuclear structure physics. ENSDF includes adopted level information for all 1950 known nuclei, and detailed data for approximately 1500 decay schemes. File organization, management, and retrieval are reviewed. An international network of data evaluation centers has been organized to provide for a four-year cycle of ENSDF revisions. Standard retrieval and display programs can prepare various tables of specific data, which can serve as a good first approximation to a complete up-to-date compilation. Appendixes list, for A > 206, nuclear levels with lifetimes > or = 1 s, strong γ rays from radioisotopes (ordered by nuclide and energy), and strong α particle emissions (similarly ordered). 8 figures

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

    International Nuclear Information System (INIS)

    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

  15. 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.

  16. Evaluated nuclear data file libraries use in nuclear-physical calculations

    International Nuclear Information System (INIS)

    Gritsaj, O.O.; Kalach, N.Yi.; Kal'chenko, O.Yi.; Kolotij, V.V.; Vlasov, M.F.

    1994-01-01

    The necessity of nuclear updated usage is founded for neutron experiment modeling calculations, for preparation of suitable data for reactor calculations and for other applications that account of detail energetic structure of cross section is required. The scheme of system to coordinate the work to collect and to prepare evaluated nuclear data on an international scale is presented. Main updated and recommended nuclear data libraries and associated computer programs are reviewed. Total neutron cross sections for 28 energetic groups calculated on the base of natural mixture iron isotopes evaluated nuclear data file (BROND-2, 1991) have been compared with BNAB-78 data. (author). 7 refs., 1 tab., 4 figs

  17. Benchmark test of evaluated nuclear data files for fast reactor neutronics application

    International Nuclear Information System (INIS)

    Chiba, Go; Hazama, Taira; Iwai, Takehiko; Numata, Kazuyuki

    2007-07-01

    A benchmark test of the latest evaluated nuclear data files, JENDL-3.3, JEFF-3.1 and ENDF/B-VII.0, has been carried out for fast reactor neutronics application. For this benchmark test, experimental data obtained at fast critical assemblies and fast power reactors are utilized. In addition to comparing of numerical solutions with the experimental data, we have extracted several cross sections, in which differences between three nuclear data files affect significantly numerical solutions, by virtue of sensitivity analyses. This benchmark test concludes that ENDF/B-VII.0 predicts well the neutronics characteristics of fast neutron systems rather than the other nuclear data files. (author)

  18. Overview of the contents of ENDF/B-VI [Evaluated Nuclear Data File

    International Nuclear Information System (INIS)

    Dunford, C.L.; Pearlstein, S.

    1989-01-01

    The sixth release of the Evaluated Nuclear Data File (ENDF/B-VI) is now being prepared for general distribution. This data file serves as the primary source of nuclear data for nuclear applications in the United States and Canada and in many other countries of the world. The data library is maintained and distributed by the National Nuclear Data Center at Brookhaven National Laboratory from evaluations provided by members of the Cross Section Evaluation Working Group (CSEWG). Unlike its predecessor, ENDF/B-V, this file will be available to all requesters without restrictions. Compared to ENDF/B-V, released more than 11 yr ago, the ENDF/B-VI data library contains significant improvements for both fission and fusion reaction design. Future work will continue with limited staffing and foreign cooperation to provide the data needed for future nuclear applications

  19. The Evaluated Nuclear Structure Data File (ENSDF). Its philosophy, content and uses

    International Nuclear Information System (INIS)

    Burrows, T.W.

    1989-04-01

    The Evaluated Nuclear Structure Data File (ENSDF) is maintained by the National Nuclear Data Center (NNDC) on behalf of international Nuclear Structure and Decay Data Network sponsored by the International Atomic Energy Agency, Vienna. For A≥44 the file is used to produce the Nuclear Data Sheets. Data for A=5 to 44 are extracted from the evaluations published in Nuclear Physics. The contents of ENSDF are briefly described as is the philosophy and methodology of ENSDF evaluations. Also discussed are the services available at various nuclear data centers and the on-line services of the NNDC. Application codes developed for use with ENSDF are described with the program RADLST used as an example. The interaction of ENSDF evaluations with other evaluations is also discussed. (author). 23 refs, 3 tabs

  20. Visual system of recovering and combination of information for ENDF (Evaluated Nuclear Data File) format libraries

    International Nuclear Information System (INIS)

    Ferreira, Claudia A.S. Velloso; Corcuera, Raquel A. Paviotti

    1997-01-01

    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 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)

  1. ENDF-102 DATA FORMATS AND PROCEDURES FOR THE EVALUATED NUCLEAR DATA FILE ENDF-6

    International Nuclear Information System (INIS)

    MCLANE, V.

    2001-01-01

    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

  2. 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.

  3. NJOY99, Data Processing System of Evaluated Nuclear Data Files ENDF Format

    International Nuclear Information System (INIS)

    2000-01-01

    1 - Description of program or function: The NJOY nuclear data processing system is a modular computer code used for converting evaluated nuclear data in the ENDF format into libraries useful for applications calculations. Because the Evaluated Nuclear Data File (ENDF) format is used all around the world (e.g., ENDF/B-VI in the US, JEF-2.2 in Europe, JENDL-3.2 in Japan, BROND-2.2 in Russia), NJOY gives its users access to a wide variety of the most up-to-date nuclear data. NJOY provides comprehensive capabilities for processing evaluated data, and it can serve applications ranging from continuous-energy Monte Carlo (MCNP), through deterministic transport codes (DANT, ANISN, DORT), to reactor lattice codes (WIMS, EPRI). NJOY handles a wide variety of nuclear effects, including resonances, Doppler broadening, heating (KERMA), radiation damage, thermal scattering (even cold moderators), gas production, neutrons and charged particles, photo-atomic interactions, self shielding, probability tables, photon production, and high-energy interactions (to 150 MeV). Output can include printed listings, special library files for applications, and Postscript graphics (plus color). More information on NJOY is available from the developer's home page at http://t2.lanl.gov/tour/tourbus.html. Follow the Tourbus section of the Tour area to find notes from the ICTP lectures held at Trieste in March 2000 on the ENDF format and on the NJOY code. NJOY contains the following modules: NJOY directs the flow of data through the other modules and contains a library of common functions and subroutines used by the other modules. RECONR reconstructs pointwise (energy-dependent) cross sections from ENDF resonance parameters and interpolation schemes. BROADR Doppler broadens and thins pointwise cross sections. UNRESR computes effective self-shielded pointwise cross sections in the unresolved energy range. HEATR generates pointwise heat production cross sections (KERMA coefficients) and radiation

  4. FEDGROUP - A program system for producing group constants from evaluated nuclear data of files disseminated by IAEA

    International Nuclear Information System (INIS)

    Vertes, P.

    1976-06-01

    A program system for calculating group constants from several evaluated nuclear data files has been developed. These files are distributed by the Nuclear Data Section of IAEA. Our program system - FEDGROUP - has certain advantage over the well-known similar codes such as: 1. it requires only a medium sized computer />or approximately equal to 20000 words memory/, 2. it is easily adaptable to any type of computer, 3. it is flexible to the input evaluated nuclear data file and to the output group constant file. Nowadays, FEDGROUP calculates practically all types of group constants needed for reactor physics calculations by using the most frequent representations of evaluated data. (author)

  5. Use of DBMS-10 for storage and retrieval of evaluated nuclear data files

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1977-01-01

    The use of a data base management system (DBMS) for storage of, and retrieval from, the many scientific data bases maintained by the National Nuclear Data Center is currently being investigated. It would appear that a commercially available DBMS package would save the Center considerable money and manpower when adding new data files to the library and in the long-term maintenance of current data files. Current DBMS technology and experience with an internal DBMS system suggests an inherent inefficiency in processing large data networks where significant portions are accessed in a sequential manner. Such a file is the Evaluated Nuclear Data File (ENDF/B), which contains many large data tables, each one normally accessed in a sequential manner. After gaining some experience and success in small applications of the commercially available DBMS package, DBMS-10, on the Center's DECsystem-10 computer, it was decided to select a large data base as a test case before making a final decision on the implementation of DBMS-10 for all data bases. The obvious approach is to utilize the DBMS to index a random-access file. In this way one is able to increase the storage and retrieval efficiency at the one-time cost of additional programing effort. 2 figures

  6. Use of DBMS-10 for storage and retrieval of evaluated nuclear data files

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1978-01-01

    The use of a data base management system (DBMS) for storage of, and retrieval from, the many scientific data bases maintained by the National Nuclear Data Center is currently being investigated. It would appear that a commercially available DBMS package would save the Center considerable money and manpower when adding new data files to our library and in the long-term maintenance of our current data files. Current DBMS technology and experience with our internal DBMS system suggests an inherent inefficiency in processing large data networks where significant portions are accessed in a sequential manner. Such a file is the Evaluated Nuclear Data File (ENDF/B) which contains many large data tables, each one normally accessed in a sequential manner. After gaining some experience and success in small applications of the commercially available DBMS package, DBMS-10, on the Center's DECsystem-10 computer, it was decided to select one of our large data bases as a test case before making a final decision on the implementation of DBMS-10 for all our data bases. The obvious approach is to utilize the DBMS to index a random access file. In this way one is able to increase the storage and retrieval efficiency at the one-time cost of additional programming effort

  7. Requirements for an evaluated nuclear data file for accelerator-based transmutation

    International Nuclear Information System (INIS)

    Koning, A.J.

    1993-06-01

    The importance of intermediate-energy nuclear data files as part of a global calculation scheme for accelerator-based transmutation of radioactive waste systems (for instance with an accelerator-driven subcritical reactor) is discussed. A proposal for three intermediate-energy data libraries for incident neutrons and protons is presented: - a data library from 0 to about 100 MeV (first priority), - a reference data library from 20 to 1500 MeV, - an activation/transmutation library from 0 to about 100 MeV. Furthermore, the proposed ENDF-6 structure of each library is given. The data needs for accelerator-based transmutation are translated in terms of the aforementioned intermediate-energy data libraries. This could be a starting point for an ''International Evaluated Nuclear Data File for Transmutation''. This library could also be of interest for other applications in science and technology. Finally, some conclusions and recommendations concerning future evaluation work are given. (orig.)

  8. Review of ENDF/B-VI Fission-Product Cross Sections[Evaluated Nuclear Data File

    Energy Technology Data Exchange (ETDEWEB)

    Wright, R.Q.; MacFarlane, R.E.

    2000-04-01

    In response to concerns raised in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 93-2, the US Department of Energy (DOE) developed a comprehensive program to help assure that the DOE maintain and enhance its capability to predict the criticality of systems throughout the complex. Tasks developed to implement the response to DNFSB recommendation 93-2 included Critical Experiments, Criticality Benchmarks, Training, Analytical Methods, and Nuclear Data. The Nuclear Data Task consists of a program of differential measurements at the Oak Ridge Electron Linear Accelerator (ORELA), precise fitting of the differential data with the generalized least-squares fitting code SAMMY to represent the data with resonance parameters using the Reich-Moore formalism along with covariance (uncertainty) information, and the development of complete evaluations for selected nuclides for inclusion in the Evaluated Nuclear Data File (ENDFB).

  9. 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.

  10. Simulation of Thermal Neutron Transport Processes Directly from the Evaluated Nuclear Data Files

    Science.gov (United States)

    Androsenko, P. A.; Malkov, M. R.

    The main idea of the method proposed in this paper is to directly extract thetrequired information for Monte-Carlo calculations from nuclear data files. The met od being developed allows to directly utilize the data obtained from libraries and seehs to be the most accurate technique. Direct simulation of neutron scattering in themmal energy range using file 7 ENDF-6 format in terms of code system BRAND has beer achieved. Simulation algorithms have been verified using the criterion x2

  11. A basic evaluated neutronic data file for elemental scandium

    International Nuclear Information System (INIS)

    Smith, A.B.; Meadows, J.W.; Howerton, R.J.

    1992-01-01

    This report documents an evaluated neutronic data file for elemental scandium, presented in the ENDF/B-VI format. This file should provide basic nuclear data essential for neutronic calculations involving elemental scandium. No equivalent file was previously available

  12. The International Evaluated Nuclear Structure Data File (ENSDF) in fundamental and applied photonuclear research

    International Nuclear Information System (INIS)

    Boboshin, I.N.; Varlamov, V.V.

    1989-04-01

    In order to provide the necessary nuclear physics data from the ENSDF file to those carrying out fundamental or applied photonuclear research a specialized software system was set up on an ES computer. A brief description of the block diagram of this software package and of one of the programs in this package (SUPER) is given. 4 refs, 6 figs

  13. Comparisons of experimental beta-ray spectra important to decay heat predictions with ENSDF [Evaluated Nuclear Structure Data File] evaluations

    International Nuclear Information System (INIS)

    Dickens, J.K.

    1990-03-01

    Graphical comparisons of recently obtained experimental beta-ray spectra with predicted beta-ray spectra based on the Evaluated Nuclear Structure Data File are exhibited for 77 fission products having masses 79--99 and 130--146 and lifetimes between 0.17 and 23650 sec. The comparisons range from very poor to excellent. For beta decay of 47 nuclides, estimates are made of ground-state transition intensities. For 14 cases the value in ENSDF gives results in very good agreement with the experimental data. 12 refs., 77 figs., 1 tab

  14. Evaluated Nuclear Structure data file: a manual for preparation of data sets

    International Nuclear Information System (INIS)

    Ewbank, W.B.; Schmorak, M.R.

    1978-02-01

    A standard input format for nuclear structure data is described. The format is sufficiently structured that bulk data can be entered efficiently. At the same time, the structure is open-ended and can accommodate most measured or deduced quantities that yield nuclear structure information

  15. Nuclear plant fire incident data file

    International Nuclear Information System (INIS)

    Sideris, A.G.; Hockenbury, R.W.; Yeater, M.L.; Vesely, W.E.

    1979-01-01

    A computerized nuclear plant fire incident data file was developed by American Nuclear Insurers and was further analyzed by Rensselaer Polytechnic Institute with technical and monetary support provided by the Nuclear Regulatory Commission. Data on 214 fires that occurred at nuclear facilities have been entered in the file. A computer program has been developed to sort the fire incidents according to various parameters. The parametric sorts that are presented in this article are significant since they are the most comprehensive statistics presently available on fires that have occurred at nuclear facilities

  16. Library of files of evaluated neutron data

    International Nuclear Information System (INIS)

    Blokhin, A.I.; Ignatyuk, A.V.; Koshcheev, V.N.; Kuz'minov, B.D.; Manokhin, V.N.; Manturov, G.N.; Nikolaev, M.N.

    1988-01-01

    It is reported about development of the evaluated neutron data files library which was recommended by the GKAE Nuclear Data Commission as the base of improving constant systems in neutron engeneering calculations. A short description of the library content is given and status of the library is pointed out

  17. An evaluated neutronic data file for bismuth

    International Nuclear Information System (INIS)

    Guenther, P.T.; Lawson, R.D.; Meadows, J.W.; Smith, A.B.; Smith, D.L.; Sugimoto, M.; Howerton, R.J.

    1989-11-01

    A comprehensive evaluated neutronic data file for bismuth, extending from 10 -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

  18. ENDF-UTILITY-CODES, codes to check and standardize data in the Evaluated Nuclear Data File (ENDF)

    International Nuclear Information System (INIS)

    Dunford, Charles L.

    2007-01-01

    1 - Description of program or function: The ENDF Utility Codes include 9 codes to check and standardize data in the Evaluated Nuclear Data File (ENDF). Four programs of this release, GETMAT, LISTEF, PLOTEF and SETMDC are no more maintained since release 6.13. The suite of ENDF utility codes includes: - CHECKR (version 7.01) is a program for checking that an evaluated data file conforms to the ENDF format. - FIZCON (version 7.02) is a program for checking that an evaluated data file has valid data and conforms to recommended procedures. - GETMAT (version 6.13) is designed to retrieve one or more materials from an ENDF formatted data file. The output will contain only the selected materials. - INTER (version 7.01) calculates thermal cross sections, g-factors, resonance integrals, fission spectrum averaged cross sections and 14.0 MeV (or other energy) cross sections for major reactions in an ENDF-6 or ENDF-5 format data file. - LISTEF (version 6.13) is designed to produce summary and annotated listings of a data file in either ENDF-6 or ENDF-5 format. - PLOTEF (version 6.13) is designed to produce graphical displays of a data file in either ENDF-5 or ENDF-6 format. The form of graphical output depends on the graphical devices available at the installation where this code will be used. - PSYCHE (version 7.02) is a program for checking the physics content of an evaluated data file. It can recognise the difference between ENDF-5 or ENDF-6 formats and performs its tests accordingly. - SETMDC (version 6.13) is a utility program that converts the source decks of programs to different computers (DOS, UNIX, LINUX, VMS, Windows). - STANEF (version 7.01) performs bookkeeping operations on a data file containing one or more material evaluations in ENDF format. The version 7.02 of the ENDF Utility Codes corrects all bugs reported to NNDC as of April 1, 2005 and supersedes all previous releases. Three codes CHECKR, STANEF, and INTER were actually ported from the 7.01 release

  19. JENDL special purpose data files and related nuclear data

    International Nuclear Information System (INIS)

    Iijima, Shungo

    1989-01-01

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

  20. Fission product yield evaluation for the USA evaluated nuclear data files

    International Nuclear Information System (INIS)

    Rider, B.F.; England, T.R.

    1994-01-01

    An evaluated set of fission product yields for use in calculation of decay heat curves with improved accuracy has been prepared. These evaluated yields are based on all known experimental data through 1992. Unmeasured fission product yields are calculated from charge distribution, pairing effects, and isomeric state models developed at Los Alamos National Laboratory. The current evaluation has been distributed as the ENDF/B-VI fission product yield data set

  1. Comparison of burnup calculation results using several evaluated nuclear data files

    International Nuclear Information System (INIS)

    Suyama, Kenya; Katakura, Jun-ichi; Nomura, Yasushi

    2002-01-01

    Burn-up calculation and comparison of the results were carried out to clarify the differences among the following latest evaluated nuclear data libraries: JENDL-3.2, ENDF/B-VI and JEF-2.2. The analyses showed that the differences seen among the current evaluated nuclear data libraries are small for evaluation of the amounts of many uranium and plutonium isotopes. However, several nuclides important for evaluation of nuclear fuel cycle as 238 Pu, 244 Cm, 149 Sm and 134 Cs showed large differences among used libraries. The chain analyses for the isotopes were conducted and the reasons for the differences were discussed. Based on the discussion, information of important cross section to obtain better agreement with the experimental results for 238 Pu, 244 Cm, 149 Sm and 134 Cs was shown. (author)

  2. Evaluation and processing of nuclear data

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1981-01-01

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

  3. Evaluation and processing of nuclear data

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1980-01-01

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

  4. An evaluated neutronic data file for elemental zirconium

    International Nuclear Information System (INIS)

    Smith, A.B.; Chiba, S.

    1994-09-01

    A comprehensive evaluated neutronic data file for elemental zirconium is derived and presented in the ENDF/B-VI formats. The derivation is based upon measured microscopic nuclear data, augmented by model calculations as necessary. The primary objective is a quality contemporary file suitable for fission-reactor development extending from conventional thermal to fast and innovative systems. This new file is a significant improvement over previously available evaluated zirconium files, in part, as a consequence of extensive new experimental measurements reported elsewhere

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

    International Nuclear Information System (INIS)

    Kinsey, R.

    1979-10-01

    These revisions to Data Formats and Procedures for the ENDF Neutron Cross Section Library, ENDF-102, pertain to the latest version of ENDF/B-V. The descriptions of the formats are brought up to date, and important procedural matters are explained

  6. Evaluated nuclear data library

    International Nuclear Information System (INIS)

    Howerton, R.J.; Dye, R.E.; Perkins, S.T.

    1981-01-01

    The Lawrence Livermore National Laboratory (LLNL) collection of evaluated data for neutron-, photon-, and charged-particle-induced reactions is maintained in a computer-oriented system. In this report we recount the history of Evaluated Nuclear Data Library, describe the methods of evaluation, and give examples of input and output representation of the data

  7. 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.

  8. Skyshine analysis using various nuclear data files

    Energy Technology Data Exchange (ETDEWEB)

    Zharkov, V.P.; Dikareva, O.F.; Kartashev, I.A.; Kiselev, A.N. [Research and Development Inst. of Power Engineering, Moscow (Russian Federation); Nomura, Y.; Tsubosaka, A. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    2000-03-01

    The calculations of the spacial distributions of dose rate for neutron and secondary photons, thermal neutron fluxes and space-energy distributions of neutron and photons near the air-ground interface were performed by MCNP and DORT codes. Different nuclear data files were used (ENDF/B-IV, ENDF/B-VI, FENDL-2, JENDL-3.2). Either the standard pointwise libraries (MCNP) or special libraries prepared by NJOY code from ENDF/B and others' files were used. Prepared multigroup coupled neutron and photon cross sections libraries for DORT code had CASK-40 group energy structures. The libraries contain pointwise or multigroup cross sections data for all elements included in the atmosphere and ground composition. The validation of the calculated results was performed with using the experimental data obtained for the series of measurements at RA reactor. (author)

  9. Skyshine analysis using various nuclear data files

    International Nuclear Information System (INIS)

    Zharkov, V.P.; Dikareva, O.F.; Kartashev, I.A.; Kiselev, A.N.; Nomura, Y.; Tsubosaka, A.

    2000-01-01

    The calculations of the spacial distributions of dose rate for neutron and secondary photons, thermal neutron fluxes and space-energy distributions of neutron and photons near the air-ground interface were performed by MCNP and DORT codes. Different nuclear data files were used (ENDF/B-IV, ENDF/B-VI, FENDL-2, JENDL-3.2). Either the standard pointwise libraries (MCNP) or special libraries prepared by NJOY code from ENDF/B and others' files were used. Prepared multigroup coupled neutron and photon cross sections libraries for DORT code had CASK-40 group energy structures. The libraries contain pointwise or multigroup cross sections data for all elements included in the atmosphere and ground composition. The validation of the calculated results was performed with using the experimental data obtained for the series of measurements at RA reactor. (author)

  10. ENDF-102 data formats and procedures for the evaluated nuclear data file ENDF-6. Revision November 1995

    International Nuclear Information System (INIS)

    McLane, V.; Dunford, C.L.; Rose, P.F.

    1995-11-01

    The 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 US 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 photo-nuclear data by partitioning the ENDF library into sublibraries. Decay data, fission product yield data, thermal scattering data, and photo-atomic data have also been formally placed in sublibraries. In addition, this rewrite represents an extensive update to the Version V manual

  11. Development of EDFSRS: evaluated data files storage and retrieval system

    International Nuclear Information System (INIS)

    Hasegawa, Akira

    1985-07-01

    EDFSRS: Evaluated Data Files Storage and Retrieval System has been developed, which is a complete service system for the evaluated nuclear data files compiled in the major three formats: ENDF/B, UKNDL and KEDAK. This system intends to give efficient loading and maintenance of evaluated nuclear data files to the data base administrators and efficient retrievals to their users not only with the easiness but with the best confidence. It can give users all of the information available in these major three formats. The system consists of more than fifteen independent programs and some 150 Mega byte data files and index files (data-base) of the loaded data. In addition it is designed to be operated in the on-line TSS (Time Sharing System) mode, so that users can get any information from their desk top terminals. This report is prepared as a reference manual of the EDFSRS. (author)

  12. Nuclear decay data files of the Dosimetry Research Group

    International Nuclear Information System (INIS)

    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

  13. Improvement of Evaluated Nuclear Data Files with Emphasis on Activation and Dosimetry Reactions

    International Nuclear Information System (INIS)

    Trkov, A.

    2013-01-01

    Researchers from the Jozef Stefan Institute are actively involved in the development of the fusion technology through the Slovenian Fusion Association. Neutronics calculations are one of the key areas of expertise and FENDL library is the reference library for the ITER device. The quality of the nuclear data library is therefore of great concern, which drives the motivation for participation in the CRP. Specific contributions to the CRP are briefly described

  14. A study of existing experimental data and validation process for evaluated high energy nuclear data. Report of task force on integral test for JENDL High Energy File in Japanese Nuclear Data Committee

    International Nuclear Information System (INIS)

    Oyama, Yukio; Baba, Mamoru; Watanabe, Yukinobu

    1998-11-01

    JENDL High Energy File (JENDL-HE) is being produced by Japanese Nuclear Data Committee (JNDC) to provide common fundamental nuclear data in the intermediate energy region for many applications concerning a basic research, an accelerator-driven nuclear waste transmutation, a fusion material study, and medical applications like the radiation therapy. The first version of JENDL-HE, which contains the evaluated nuclear data up to 50 MeV, is planned to release in 1998. However, a method of integral test with which we can validate the high-energy nuclear data file has not been established. The validation of evaluated nuclear data through the integral tests is necessary to promote utilization of JENDL-HE. JNDC set up a task force in 1997 to discuss the problems concerning the integral tests of JENDL-HE. The task force members have surveyed and studied the current status of the problems for a year to obtain a guideline for development of the high-energy nuclear database. This report summarizes the results of the survey and study done by the task force for JNDC. (author)

  15. Guidebook for the ENDF/B-V nuclear data files

    International Nuclear Information System (INIS)

    Magurno, B.A.; Kinsey, R.R.; Scheffel, F.M.

    1982-07-01

    The National Nuclear Data Center (NNDC) has provided the Electric Power Research Institute (EPRI) with a convenient reference/guidebook to nuclear data derived from the Evaluated Nuclear Data File, Version V (ENDF/B-V). The main part of the edition consists of plots of the major cross sections for each of the General Purpose Nuclides. These plots are reconstructed from the resonance parameters and background cross sections given in the library. The resolution and display format have been selected to show general trends in the data. Following the section for individual nuclides, an intercomparison of cross section ratios (plots of eta and α values) is provided for the major fissile nuclei. The final section contains a table of nuclide properties derived from the data files. Included are thermal (2200m/sec and maxwellian averaged) cross sections, g factors, infinitely dilute resonance integrals and fission spectrum averages

  16. Japanese Evaluated Nuclear Data Library, version-3

    International Nuclear Information System (INIS)

    Shibata, Keiichi; Nakagawa, Tsuneo; Asami, Tetsuo

    1990-06-01

    The general purpose file of the third version of Japanese Evaluated Nuclear Data Library, JENDL-3, has been compiled by the JAERI Nuclear Data Center in cooperation with the Japanese Nuclear Data Committee. It contains neutron nuclear data for 171 nuclides which are needed for design of fission and fusion reactors and for shielding calculation. In the JENDL-3 evaluation, much effort was devoted to improve reliability of high-energy data for fusion application and to include gamma-ray production data. Theoretical calculations played an important role in achieving these purposes. A special method called simultaneous evaluation was adopted to determine important cross sections of fissile and fertile nuclides. This report presents a general description for the evaluation of light, medium-heavy and heavy nuclide data. Also given are the descriptive data for each nuclide contained in the File 1 part of JENDL-3. (author)

  17. ZZ ENDF/B-V, Evaluated Nuclear Data File Version 5

    International Nuclear Information System (INIS)

    Kinsey, R.; Magurno, B.A.; Young, P.G.

    2006-01-01

    -152, 57-La-138-155, 58-Ce-140-157, 59-Pr-141-142, 59-Pr-142m, 59-Pr-143-144, 59-Pr-144m, 59-Pr-145-159, 60-Nd-142-161, 61-Pm-147-148, 61-Pm-148m, 61-Pm-149-152, 61-Pm-152m, 61-Pm-152N, 61-Pm-153-154, 61-Pm-154m, 61-Pm-155-162, 62-Sm-144-165, 63-Eu-151-152, 63-Eu-152m, 63-Eu-152N, 63-Eu-153-154, 63-Eu-154m, 63-Eu-155-166, 64-Gd-152-165, 65-Tb-159-165, 66-Dy-160-165, 66-Dy-165m, 66-Dy-166, 67-Ho-165-166, 67-Ho-166m, 68-Er-166-167, 68-Er-167m, 71-Lu-175-176, 72-Hf-174, 72-Hf-176-181, 73-Ta-181-182, 74-W-182-184, 74-W-186-187, 75-Re-185, 75-Re-187, 79-Au-197, 81-Tl-208, 82-Pb-212-213, 83-Bi-209, 83-Bi-212, 84-Po-216, 86-Rn-220, 88-Ra-224, 90-Th-228, 90-Th-230-233, 91-Pa-231-233, 92-U-232-239, 93-Np-236, 93-Np-236m, 93-Np-237-239, 94-Pu-236-244, 95-Am-240-242, 95-Am-242m, 95-Am-243-244, 95-Am-244m, 96-Cm-241-249, 97-Bk-249-250, 98-Cf-249-253, 99-Es-253 Origin: BNL; Weighting Spectrum: none. Contains the evaluated neutron cross-section data for 90 nuclides, issued by the National Nuclear Data Center at the Brookhaven National Laboratory (NNDC-BNL) in 1979

  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

    International Nuclear Information System (INIS)

    Uddin, M.N.; Sarker, M.M.; Khan, M.J.H.; Islam, S.M.A.

    2009-01-01

    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 2 -1, BAPL-UO 2 -2 and BAPL-UO 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. Processing and validation of intermediate energy evaluated data files

    International Nuclear Information System (INIS)

    2000-01-01

    Current accelerator-driven and other intermediate energy technologies require accurate nuclear data to model the performance of the target/blanket assembly, neutron production, activation, heating and damage. In a previous WPEC subgroup, SG13 on intermediate energy nuclear data, various aspects of intermediate energy data, such as nuclear data needs, experiments, model calculations and file formatting issues were investigated and categorized to come to a joint evaluation effort. The successor of SG13, SG14 on the processing and validation of intermediate energy evaluated data files, goes one step further. The nuclear data files that have been created with the aforementioned information need to be processed and validated in order to be applicable in realistic intermediate energy simulations. We emphasize that the work of SG14 excludes the 0-20 MeV data part of the neutron evaluations, which is supposed to be covered elsewhere. This final report contains the following sections: section 2: a survey of the data files above 20 MeV that have been considered for validation in SG14; section 3: a summary of the review of the 150 MeV intermediate energy data files for ENDF/B-VI and, more briefly, the other libraries; section 4: validation of the data library against an integral experiment with MCNPX; section 5: conclusions. (author)

  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. 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.

  2. Impact of up-to-date evaluated nuclear data files on the Monte-Carlo analysis results of metallic fueled BFS critical assemblies

    International Nuclear Information System (INIS)

    Yoo, Jaewoon; Kim, Do-Heon; Kim, Sang-Ji; Kim, Yeong-Il

    2009-01-01

    Three metallic fueled BFS critical assemblies, BFS-73-1, BFS-75-1, and BFS-55-1 were analyzed by using the Monte-Carlo analysis code MCNP4C with five different evaluated data files, ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, JENDL-AC and ENDF/B-VI.6. The impacts of microscopic cross sections in the up-to-date evaluated nuclear data files were clarified by the analyses. The update of Zr cross section leads to the calculated k-effective lower than that of ENDF/B-VI.6. The revision of U-238 inelastic scattering cross section makes large difference in the predicted k-effectives between the libraries, which depends on the amount of the contribution of the inelastic cross sections change and the compensation of other reaction types. The results of the spectral indices and reaction rate ratios shows the improvement of the up-to-date evaluated nuclear data files for the U-238, Np-237, Pu-240 fission reactions, however, there are still need of further improvement for other minor actinide cross sections. The heterogeneity effects involved on the k-effective and relative fission rate distribution were evaluated in this study, which can be used as the correction factor for constructing the homogeneous benchmark configuration while keeping the consistency with the actual critical experiment. (author)

  3. The Jeff evaluated nuclear data project

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J.; Duijvestijn, M.C.; Hogenbirk, A.; Van der Marck, S.C.; Avrigeanu, M.; Avrigeanu, V.; Batistoni, P.; Pillon, M.; Bauge, E.; Bersillon, O.; Dos-Santos-Uzarralde, P.; Lopez Jimenez, M.J.; Morillon, B.; Romain, P.; Be, M.M.; Duchemin, B.; Huynh, T.D.; Jouanne, C.; Mounier, C.; Bem, P.; Bernard, D.; Bouland, O.; Courcelle, A.; Dupont, E.; Jacqmin, R.; Litaize, O.; Noguere, G.; Saint Jean, C. de; Santamarina, A.; Serot, O.; Sublet, J.Ch.; Bidaud, A.; Dean, C.J.; Perry, R.J.; Duhamel, I.; Nouri, A.; Gunsing, F.; Ridikas, D.; Fischer, U.; Leichtle, D.; Pereslavtsev, P.; Simakov, S.; Forrest, R.A.; Haeck, W.; Henriksson, H.; Kodeli, I.; Nordborg, C.; Rugama, Y.; Sartori, E.; Keinert, J.; Mattes, M.; Kellett, M.A.; Nichols, A.L.; Kopecky, J.; Leeb, H.; Leppanen, J.; Menapace, E.; Pescarini, M.; Mills, R.W.; Perel, R.L.; Plompen, A.J.M.; Rullhusen, P.; Seidel, K.; Tagesen, S.; Vonach, H.; Trkov, A

    2008-07-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. JEFF-3.1 comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, the decay data and fission yield sub-libraries, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory and shielding of thermal and fast systems. Compared with earlier releases, JEFF-3.1 provides improved performance with respect to a variety of scientific and industrial applications. Following on from the public release of JEFF-3.1, the French nuclear power industry has selected this suite of nuclear applications libraries for inclusion in their production codes. (authors)

  4. The Jeff evaluated nuclear data project

    International Nuclear Information System (INIS)

    Koning, A.J.; Duijvestijn, M.C.; Hogenbirk, A.; Van der Marck, S.C.; Avrigeanu, M.; Avrigeanu, V.; Batistoni, P.; Pillon, M.; Bauge, E.; Bersillon, O.; Dos-Santos-Uzarralde, P.; Lopez Jimenez, M.J.; Morillon, B.; Romain, P.; Be, M.M.; Duchemin, B.; Huynh, T.D.; Jouanne, C.; Mounier, C.; Bem, P.; Bernard, D.; Bouland, O.; Courcelle, A.; Dupont, E.; Jacqmin, R.; Litaize, O.; Noguere, G.; Saint Jean, C. de; Santamarina, A.; Serot, O.; Sublet, J.Ch.; Bidaud, A.; Dean, C.J.; Perry, R.J.; Duhamel, I.; Nouri, A.; Gunsing, F.; Ridikas, D.; Fischer, U.; Leichtle, D.; Pereslavtsev, P.; Simakov, S.; Forrest, R.A.; Haeck, W.; Henriksson, H.; Kodeli, I.; Nordborg, C.; Rugama, Y.; Sartori, E.; Keinert, J.; Mattes, M.; Kellett, M.A.; Nichols, A.L.; Kopecky, J.; Leeb, H.; Leppanen, J.; Menapace, E.; Pescarini, M.; Mills, R.W.; Perel, R.L.; Plompen, A.J.M.; Rullhusen, P.; Seidel, K.; Tagesen, S.; Vonach, H.; Trkov, A.

    2008-01-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. JEFF-3.1 comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, the decay data and fission yield sub-libraries, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory and shielding of thermal and fast systems. Compared with earlier releases, JEFF-3.1 provides improved performance with respect to a variety of scientific and industrial applications. Following on from the public release of JEFF-3.1, the French nuclear power industry has selected this suite of nuclear applications libraries for inclusion in their production codes. (authors)

  5. Nuclear structure data file. A manual for preparation of data sets

    International Nuclear Information System (INIS)

    Ewbank, W.B.; Schmorak, M.R.; Bertrand, F.E.; Feliciano, M.; Horen, D.J.

    1975-06-01

    The Nuclear Data Project at ORNL is building a computer-based file of nuclear structure data, which is intended for use by both basic and applied users. For every nucleus, the Nuclear Structure Data File contains evaluated nuclear structure information. This manual describes a standard input format for nuclear structure data. The format is sufficiently structured that bulk data can be entered efficiently. At the same time, the structure is open-ended and can accommodate most measured or deduced quantities that yield nuclear structure information. Computer programs have been developed at the Data Project to perform consistency checking and routine calculations. Programs are also used for preparing level scheme drawings. (U.S.)

  6. The file of evaluated decay data in ENDF/B

    International Nuclear Information System (INIS)

    Reich, C.W.

    1991-01-01

    One important application of nuclear decay data is the Evaluated Nuclear Data File/B (ENDF/B), the base of evaluated nuclear data used in reactor research and technology activities within the United States. The decay data in the Activation File (158 nuclides) and the Actinide File (108 nuclides) excellently represent the current status of this information. In particular, the half-lives and gamma and alpha emission probabilities, quantities that are so important for many applications, of the actinide nuclides represent a significant improvement over those in ENDF/B-V because of the inclusion of data produced by an International Atomic Energy Agency Coordinated Research Program. The Fission Product File contains experimental decay data on ∼510 nuclides, which is essentially all for which a meaningful number of data are available. For the first time, delayed-neutron spectra for the precursor nuclides are included. Some hint of problems in the fission product data base is provided by the gamma decay heat following a burst irradiation of 239 Pu

  7. Nuclear data evaluation method and evaluation system

    International Nuclear Information System (INIS)

    Liu Tingjin

    1995-01-01

    The evaluation methods and Nuclear Data Evaluation System have been developed in China. A new version of the system has been established on Micro-VAX2 computer, which is supported by IAEA under the technology assistance program. The flow chart of Chinese Nuclear Data Evaluation System is shown out. For last ten years, the main efforts have been put on the double differential cross section, covariance data and evaluated data library validation. The developed evaluation method and Chinese Nuclear Data Evaluation System have been widely used at CNDC and in Chinese Nuclear Data Network for CENDL. (1 tab., 15 figs.)

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

    International Nuclear Information System (INIS)

    Herman, M.

    2009-01-01

    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.

  9. 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.

  10. Principles and problems in neutron nuclear data evaluation

    International Nuclear Information System (INIS)

    Schmidt, J.J.

    1967-01-01

    The history of neutron nuclear data evaluation is briefly summarized. The physical problems involved in nuclear data evaluation, such as discrepancies and inconsistencies between different experimental data sets and gaps in experimental information, are discussed. The discrepancies in the capture cross-section data for molybdenum and iron are chosen to illustrate the great difficulties in systematizing and automatizing the evaluation process. The technical problems of data evaluation, such as computer storage and the establishment of nuclear data files, are not discussed. (author)

  11. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Gil, Choong Sup [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1993-12-01

    In nuclear or shielding design analysis for reactors including nuclear facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multigroup constant library using the newly compiled data files and the code systems. As the results of this project, JEF-2.2 which is latest version of Joint Evaluated File developed at OECD/NEA was compiled and COMPLOT and EVALPLOT utility codes were installed in personal computer, which are able to draw ENDF/B-formatted nuclear data for comparison and check. Computer system (NJOY/ACER) for generating continuous energy Monte Carlo code MCNP library was established and the system was validated by analyzing a number of experimental data. (Author).

  12. Nuclear Reaction Data File for Astrophysics (NRDF/A) in Hokkaido University Nuclear Reaction Data Center

    International Nuclear Information System (INIS)

    Kato, Kiyoshi; Kimura, Masaaki; Furutachi, Naoya; Makinaga, Ayano; Togashi, Tomoaki; Otuka, Naohiko

    2010-01-01

    The activities of the Japan Nuclear Reaction Data Centre is explained. The main task of the centre is data compilation of Japanese nuclear reaction data in collaboration of the International Network of Nuclear Reaction Data Centres. As one of recent activities, preparation of a new database (NRDF/A) and evaluation of astronuclear reaction data are reported. Collaboration in the nuclear data activities among Asian countries is proposed.

  13. A data compression algorithm for nuclear spectrum files

    International Nuclear Information System (INIS)

    Mika, J.F.; Martin, L.J.; Johnston, P.N.

    1990-01-01

    The total space occupied by computer files of spectra generated in nuclear spectroscopy systems can lead to problems of storage, and transmission time. An algorithm is presented which significantly reduces the space required to store nuclear spectra, without loss of any information content. Testing indicates that spectrum files can be routinely compressed by a factor of 5. (orig.)

  14. Nuclear data, their importance and evaluation

    International Nuclear Information System (INIS)

    Schmidt, J.J.

    1980-01-01

    Nuclear data comprize all quantitative results of nuclear physics investigations and can be subdivided in the three areas of nuclear structure, nuclear decay and nuclear reaction data. For the purposes of fission and fusion reactor design mostly neutron reaction data are needed, while for the nuclear fuel cycle outside the reactor and for a large variety of ''non-energy'' scientific applications a number of photonuclear and charged particle nuclear reaction data and of nuclear structure and decay data are needed, in addition to selected neutron nuclear reaction data. To meet the needs of nuclear science and technology for accurate nuclear data, comprehensive computer libraries of evaluated nuclear data have been built up from evaluation of a massive volume of experimental data complemented by data calculated from nuclear theory. The basic characteristics and requirements of evaluated data libraries are discussed and evaluation sources and methods illustrated with the example of a few important neutron nuclear reactions. International mechanisms have been developed, coordinated by the IAEA Nuclear Data Section with the cooperation of many nuclear data centres and groups, for the efficient dissemination of bibliographic and numerical experimental and evaluated nuclear data to data users in the whole world. (author)

  15. Manual on usage of the Nuclear Reaction Data File (NRDF)

    International Nuclear Information System (INIS)

    1984-10-01

    In the computer in the Institute for Nuclear Study, University of Tokyo, there is set up a Nuclear Reaction Data File (NRDF) which has been built in Hokkaido University. While the data base is growing year after year, its trial usage is for the purpose of joint utilization by educational institutions. In section 1, examples of the retrieval are presented to have the user familiarize with NRDF. In section 2, the terms used in retrieval are given in table. Then, in section 3, as a summary of the examples, structure of the retrieval commands is explained. In section 4, for the retrieval results on a CRT, cautions in reading are given. Finally, in section 5, general cautions in usage of NRDF are given. (Mori, K.)

  16. Evaluation and analysis of nuclear resonance data

    International Nuclear Information System (INIS)

    Frohner, F.H.

    2000-01-01

    A probabilistic foundations of data evaluation are reviewed, with special emphasis on parameter estimation based on Bayes' theorem and a quadratic loss function, and on modern methods for the assignment of prior probabilities. The data reduction process leading from raw experimental data to evaluated computer files of nuclear reaction cross sections is outlined, with a discussion of systematic and statistical errors and their propagation and of the generalized least squares formalism including prior information and nonlinear theoretical models. It is explained how common errors induce correlations between data, what consequences they have for uncertainty propagation and sensitivity studies, and how evaluators can construct covariance matrices from the usual error information provided by experimentalists. New techniques for evaluation of inconsistent data are also presented. The general principles are then applied specifically to the analysis and evaluation of neutron resonance data in terms of theoretical models - R-matrix theory (and especially its practically used multi-level Breit-Wigner and Reich-Moore variants) in the resolved region, and resonance-averaged R-matrix theory (Hauser-Feshbach theory with width-fluctuation corrections) in the unresolved region. Complications arise because the measured transmission data, capture and fission yields, self-indication ratios and other observables are not yet the wanted cross sections. These are obtained only by means of parametrisation. The intervening effects - Doppler and resolution broadening, self-shielding, multiple scattering, backgrounds, sample impurities, energy-dependent detector efficiencies, inaccurate reference data etc - are therefore also discussed. (author)

  17. JEF-2. The evaluated Nuclear Data Library of the NEA Data Bank

    International Nuclear Information System (INIS)

    Lemmel, H.D.; Schwerer, O.

    1993-01-01

    This document summarizes the contents of JEF-2, the Joint Evaluated File of nuclear data compiled by the OECD Nuclear Energy Agency Data Bank, finalized in 1992 and released in 1993. The entire library or retrievals of selected materials are available on magnetic tape from the IAEA Nuclear Data Section free of charge. (author)

  18. JEF-1: The Evaluated Nuclear Data Library of the NEA Data Bank

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1991-04-01

    This document summarizes the contents of JEF-1, the Joint Evaluated File of nuclear data compiled by the OECD Nuclear Energy Agency Data Bank, finalized in 1986 and released in 1990. The entire library or retrievals of selected materials are available on magnetic tape from the IAEA Nuclear Data Section free of charge. (author)

  19. JEF-1. The evaluated nuclear data library of the NEA Data Bank

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1990-09-01

    This document summarizes the contents of JEF-1, the Joint Evaluated File of nuclear data compiled by the OECD Nuclear Energy Agency Data Bank, finalized in 1986 and released in 1990. The entire library or retrievals of selected materials are available on magnetic tape from the IAEA Nuclear Data Section free of charge. (author)

  20. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Lee, Jong Tae; Min, Byung Joo; Gil, Choong Sup [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

    1991-01-01

    In nuclear or shielding design analysis for reactors or other facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multi- group constant library using the newly compiled data files and the code systems. As the results of this project, ENDF/B-VI Supplementary File including important nuclides, JENDL-3.1 and JEF-1 were compiled, and ENDF-6 international computer file format for evaluated nuclear data and its processing system NJOY89.31 were tested with ENDF/B-VI data. In order to test an applicability of the newly released data to thermal reactor problems, a number of benchmark calculations were performed, and the results were analyzed. Since preliminary benchmark testing of thermal reactor problems have been made the newly compiled data are expected to be positively used to develop advanced reactors. (Author).

  1. Nuclear data evaluation and group constant generation for reactor analysis

    International Nuclear Information System (INIS)

    Kim, Jung Do; Lee, Jong Tae; Min, Byung Joo; Gil, Choong Sup

    1991-01-01

    In nuclear or shielding design analysis for reactors or other facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multi- group constant library using the newly compiled data files and the code systems. As the results of this project, ENDF/B-VI Supplementary File including important nuclides, JENDL-3.1 and JEF-1 were compiled, and ENDF-6 international computer file format for evaluated nuclear data and its processing system NJOY89.31 were tested with ENDF/B-VI data. In order to test an applicability of the newly released data to thermal reactor problems, a number of benchmark calculations were performed, and the results were analyzed. Since preliminary benchmark testing of thermal reactor problems have been made the newly compiled data are expected to be positively used to develop advanced reactors. (Author)

  2. Neutron nuclear data evaluation for actinide nucleic

    International Nuclear Information System (INIS)

    Chen Guochang; Yu Baosheng; Duan Junfeng; Ge Zhigang; Cao Wentian; Tang Guoyou; Shi Zhaomin; Zou Yubin

    2010-01-01

    The nuclear data with high accuracy for minor actinides are playing an important role in nuclear technology applications, including reactor design and operation, fuel cycle concepts, estimation of the amount of minor actinides in high burn-up reactors and the minor actinides transmutation. Through describe the class of nuclear data and nuclear date library, and introduce the procedure of neutron nuclear data evaluation. 234 U(n, f) and 237 Np(n, 2n) reaction experimental data evaluation was evaluated. The fission nuclear data are updated and improved. (authors)

  3. Program SIGMA1 (version 79-1): Doppler broaden evaluated cross sections in the evaluated nuclear data file/version B (ENDF/B) format

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1979-01-01

    Program SIGMA1 Doppler-broadens evaluated cross sections in the ENDF/B format. The program requires that input cross sections be tabulated as linearly interpolable functions of energy in ENDF/B File 3; broadened cross sections, in this same form, replace the original values in the output tape. This report describes the methods used in the code and serves as a user's guide. A listing of the source deck is available on request

  4. Establishment of nuclear data evaluation system (I)

    International Nuclear Information System (INIS)

    Chang, Jong Hwa; Lee, Chang Kun; Kim, Jeong Do; Kim, Young Sik; Kim, Young Jin; Kim, Hyung Guk; Kil, Chung Sup; Kim, Kang Suk

    1994-08-01

    Nuclear data is fundamental data for development of new type of nuclear, upgrade of nuclear fuel, treatment of radwaste, research on fusion reactor, radioisotope usage, and nuclear medical therapy. Nuclear data is produced with experiments. However rack of experimental data for thousands of nuclides and various reaction types makes it essential to do statistical evaluation and theoretical interpolation. This study is intended to join international cooperation after establishing domestic basis for nuclear data evaluation work. This project is the first year of five year plan to do followings: 1) Establishment of database system to collect experimental data, 2) Setup of computer assistance system for evaluation work, 3) Verification of established system by test evaluation of selected nuclide reaction. The system has a collection of mass data of nuclides, computer codes for test evaluation of total cross section of 0-16 and collection of EXFOR format data for 0-16. This system will be improved continuously on next years. (Author)

  5. Development of data file system for cardiovascular nuclear medicine

    International Nuclear Information System (INIS)

    Hayashida, Kohei; Nishimura, Tsunehiko; Uehara, Toshiisa; Nisawa, Yoshifumi.

    1985-01-01

    A computer-assisted filing system for storing and processing data from cardiac pool scintigraphy and myocardial scintigraphy has been developed. Individual patient data are stored with his (her) identification number (ID) into floppy discs successively in order of receiving scintigraphy. Data for 900 patients can be stored per floppy disc. Scintigraphic findings can be outputted in a uniform file format, and can be used as a reporting format. Output or retrieval of filed individual patient data is possible according to each examination, disease code or ID. This system seems to be used for prospective study in patients with cardiovascular diseases. (Namekawa, K.)

  6. Status of thorium cycle nuclear data evaluations: Comparison of cross-section line shapes of JENDL-3 and ENDF-B-VI files for 230Th, 232Th, 231Pa, 233Pa, 232U, 233U and 234U

    International Nuclear Information System (INIS)

    Ganesan, S.; McLaughlin, P.K.

    1992-02-01

    Since 1990, one of the most interesting developments in the field of nuclear data for nuclear technology applications is that several new evaluated data files have been finalized and made available to the International Atomic Energy Agency (IAEA) for distribution to its Member States. Improved evaluated nuclear data libraries such as ENDF/B-VI from the United States and JENDL-3 from Japan were developed over a period of 10-15 years. This report is not an evaluation of the evaluations. The report as presented here gives a first look at the cross section line shapes of the isotopes that are important to the thorium fuel cycle derived from the two recently evaluated data files: JENDL-3 and ENDF/B-VI. The basic evaluated data files JENDL-3 and ENDF/B-VI were point-processed successfully using the codes LINEAR and RECENT. The point data were multigrouped in three different group structures using the GROUPIE code. Graphs of intercomparisons of cross section line shapes of JENDL-3 and ENDF/B-VI are presented in this paper for the following isotopes of major interest to studies of the thorium fuel cycle: 230 Th, 232 Th, 231 Pa, 233 Pa, 232 U, 233 U and 234 U. Comparisons between JENDL-3 and ENDF/B-VI which were performed at the point and group levels show large discrepancies in various cross sections. We conclude this report with a general remark that it is necessary to perform sensitivity studies to assess the impacts of the discrepancies between the two different sets of data on calculated reactor design and safety parameters of specific reactor systems and, based on the results of such sensitivity studies, to undertake new tasks of evaluations. (author). 2 refs, 245 figs, 8 tabs

  7. Design and creation of a direct access nuclear data file

    International Nuclear Information System (INIS)

    Charpentier, P.

    1981-06-01

    General considerations on the structure of instructions and files are reviewed. Design, organization and mode of use of the different files: instruction file, index files, inverted files, automatic analysis and inquiry programs are examined [fr

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

    International Nuclear Information System (INIS)

    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.; Authier, N.; Casoli, P.; Richard, B.

    2012-01-01

    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.)

  9. 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.)

  10. Modern Nuclear Data Evaluation with the TALYS Code System

    Science.gov (United States)

    Koning, A. J.; Rochman, D.

    2012-12-01

    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.

  11. Modern Nuclear Data Evaluation with the TALYS Code System

    International Nuclear Information System (INIS)

    Koning, A.J.; Rochman, D.

    2012-01-01

    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.

  12. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Gil, Choong Sup; Min, Byung Joo; Lee, Jong Tai [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1993-01-01

    In nuclear or shielding design analysis for reactors or other facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multi-group constant library using the newly compiled data files and the code systems. As the results of this project, the latest version of NJOY nuclear data processing system, NJOY91.38 which is capable of processing data in ENDF-6 format, was compiled and installed in Cyber 960-31(OS : NOS/VE) and HP710 workstation. A 50-group constant library for fast reactor was generated with NJOY91.38 using evaluated data from JEF-1 and benchmark test of this library was performed. The newly generated library has been found to do an excellent job of calculating integral quantities for fast critical assemblies and is expected to be positively used to develop fast reactors. (Author).

  13. International evaluated neutron nuclear data libraries

    International Nuclear Information System (INIS)

    Liu Tingjin

    2001-01-01

    The current status of five major evaluated neutron nuclear data libraries in the world are introduced. They are ENDF/B-6 (U. S. A.), JENDL-3.2 (Japan), JEF-2.2 (Europe), CENDL-2.1 (China), BROND-2 (Russia). The developing trend of the international neutron evaluated nuclear data library is discussed. How to get and use these data for the domestic users is given

  14. 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.

  15. Nuclear data and related services

    International Nuclear Information System (INIS)

    Tuli, J.K.

    1985-01-01

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

  16. 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.

  17. Experimental (Network) and Evaluated Nuclear Reaction Data at NDS

    International Nuclear Information System (INIS)

    Otsuka, N.; Semkova, V.; Simakov, S.P.; Zerkin, V.

    2011-01-01

    Dr Simakov of Nuclear Data Services Unit in the Nuclear Data Section (NDS) gave a brief overview of the data compilation and evaluation activities in the nuclear data community: experimental nuclear reaction data (EXFOR, http://www-nds.iaea.org/exfor/) and evaluated nuclear reaction data (ENDF, http://www-nds.iaea.org/endf). The International Network of Nuclear Reaction Data Centres (NRDC) coordinated by NDS includes 14 Centres in 8 Countries (China, Hungary, India, Japan, Korea, Russian, Ukraine, USA) and 2 International Organizations (NEA, IAEA). It had the first meeting of four core centres (Brookhaven, Saclay, Obninsk, Vienna) in 1966 and the EXFOR was adopted as an official data exchange format. In 2000, IAEA implemented the EXFOR database as a relational multiform database and the EXFOR is a trusted, increasing and living database with 19100 experimental works (as of September 2011) and 141600 data tables. The EXFOR provides a compilation control system for selection of articles and compilation of data and the NRDC home page provides manuals, documents and codes. The nuclear data can be retrieved by the web-retrieval system or distributed on a DVD on request. The EXFOR data play a critical role in the development of evaluated nuclear reaction data. There are several major general purpose libraries: ENDF (US), CENDL (China), JEFF (EU), JENDL (Japan) and RUSFOND (Russia). In addition, there are special libraries for particular applications: EAF (European Activation File), FENDL (Fusion Evaluated Nuclear Data Library for ITER neutronics), IBANDL (Ion Beam Analysis Nuclear Data Library for surface analysis of solids), IRDF, DXS (Dosimetry, radiation damage and gas production data) and Medical portal. Dr V. Zerkin of NDS demonstrated the data retrieval from the EXFOR database and the ENDF library.

  18. Experimental (Network) and Evaluated Nuclear Reaction Data at NDS

    Energy Technology Data Exchange (ETDEWEB)

    Otsuka, N; Semkova, V; Simakov, S P; Zerkin, V [Nuclear Data Services Unit, Nuclear Data Section, IAEA, Vienna (Austria)

    2011-11-15

    Dr Simakov of Nuclear Data Services Unit in the Nuclear Data Section (NDS) gave a brief overview of the data compilation and evaluation activities in the nuclear data community: experimental nuclear reaction data (EXFOR, http://www-nds.iaea.org/exfor/) and evaluated nuclear reaction data (ENDF, http://www-nds.iaea.org/endf). The International Network of Nuclear Reaction Data Centres (NRDC) coordinated by NDS includes 14 Centres in 8 Countries (China, Hungary, India, Japan, Korea, Russian, Ukraine, USA) and 2 International Organizations (NEA, IAEA). It had the first meeting of four core centres (Brookhaven, Saclay, Obninsk, Vienna) in 1966 and the EXFOR was adopted as an official data exchange format. In 2000, IAEA implemented the EXFOR database as a relational multiform database and the EXFOR is a trusted, increasing and living database with 19100 experimental works (as of September 2011) and 141600 data tables. The EXFOR provides a compilation control system for selection of articles and compilation of data and the NRDC home page provides manuals, documents and codes. The nuclear data can be retrieved by the web-retrieval system or distributed on a DVD on request. The EXFOR data play a critical role in the development of evaluated nuclear reaction data. There are several major general purpose libraries: ENDF (US), CENDL (China), JEFF (EU), JENDL (Japan) and RUSFOND (Russia). In addition, there are special libraries for particular applications: EAF (European Activation File), FENDL (Fusion Evaluated Nuclear Data Library for ITER neutronics), IBANDL (Ion Beam Analysis Nuclear Data Library for surface analysis of solids), IRDF, DXS (Dosimetry, radiation damage and gas production data) and Medical portal. Dr V. Zerkin of NDS demonstrated the data retrieval from the EXFOR database and the ENDF library.

  19. Nuclear data online

    International Nuclear Information System (INIS)

    McLane, V.

    1997-01-01

    The National Nuclear Data Center (NNDC) Online Data Service, available since 1986, is continually being upgraded and expanded. Most files are now available for access through the World Wide Web. Bibliographic, experimental, and evaluated data files are available containing information no neutron, charged-particle, and photon-induced nuclear reaction data, as well as nuclear decay and nuclear structure information. An effort is being made through the world-wide Nuclear Reaction Data Centers collaboration to make the charged-particle reaction data libraries as complete as possible. The data may be downloaded or viewed both as plots or as tabulated data. A variety of output formats are available for most files

  20. Program LINEAR (version 79-1): linearize data in the evaluated nuclear data file/version B (ENDF/B) format

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1979-01-01

    Program LINEAR converts evaluated cross sections in the ENDF/B format into a tabular form that is subject to linear-linear interpolation in energy and cross section. The code also thins tables of cross sections already in that form (i.e., removes points not needed for linear interpolability). The main advantage of the code is that it allows subsequent codes to consider only linear-linear data. A listing of the source deck is available on request

  1. Nuclear data evaluation for medium and heavy nuclei

    International Nuclear Information System (INIS)

    Mizumoto, Motoharu

    1988-01-01

    Present status of nuclear data evaluation works for medium and heavy nuclei is described in this paper. These data are being prepared for JENDL-3 (Japanese Evaluated Nuclear Data Library-Version 3). At present, about a half of the data files, which are expected to be stored in the final library, has been brought into a temporary library called JENDL-3T. The remaining works and additional revisions are still needed to be made in order to finalize the data library as JENDL-3. Special emphases have been put on the high energy neutron data for which the previous JENDL-2 had some inadequacies, and gamma-ray production cross sections have been newly evaluated. Systematic and consistent evaluations have been intended for the new evaluations. (author)

  2. Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X and NJOY2016

    Directory of Open Access Journals (Sweden)

    Kabach Ouadie

    2017-12-01

    Full Text Available To validate the new Evaluated Nuclear Data File (ENDF/B-VIII.0β4 library, 31 different critical cores were selected and used for a benchmark test of the important parameter keff. The four utilized libraries are processed using Nuclear Data Processing Code (NJOY2016. The results obtained with the ENDF/B-VIII.0β4 library were compared against those calculated with ENDF/B-VI.8, ENDF/B-VII.0, and ENDF/B-VII.1 libraries using the Monte Carlo N-Particle (MCNP(X code. All the MCNP(X calculations of keff values with these four libraries were compared with the experimentally measured results, which are available in the International Critically Safety Benchmark Evaluation Project. The obtained results are discussed and analyzed in this paper.

  3. INDXENDF: A PC code for indexing nuclear data files in ENDF-6 format

    International Nuclear Information System (INIS)

    Silva, O.O. de; Corcuera, R.P.; Ferreira, P.A.; Moraes Cunha, M. de.

    1992-01-01

    The PC code INDXENDF which creates visual or printed indexes of nuclear data files in ENDF-6 format, is available from the IAEA Nuclear Data Section on a PC diskette, free of charge upon request. The present document describes the features of this code. (author). 11 refs, 9 figs

  4. Program EVALPLOT (Version 79-1): plot data in the Evaluated-Nuclear-Data File/Version B (ENDF/B) format

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1979-01-01

    Program EVALPLOT is designed to plot evaluated cross sections in the ENDF/B format. The program plots cross sections, angular distributions, energy distributions, and parameters (e.g., μ-bar, xi-bar, and ν-bar). 16 figures, 2 tables

  5. Techniques used for charged particle nuclear data evaluation at CNDC

    International Nuclear Information System (INIS)

    Zhuang Youxiang; Sun Zuxun

    1993-01-01

    The methods and techniques used for Charged Particle Nuclear Data (CPND) evaluation at Chinese Nuclear Data Center (CNDC) are summarized, including compilation and evaluation of experimental data, nuclear reaction theory and model calculation, systematics research and comprehensive recommendation etc

  6. Nuclear theory for fast neutron nuclear data evaluation

    International Nuclear Information System (INIS)

    1988-11-01

    The proceedings contain all invited and contributed papers presented at the Advisory Group Meeting on Nuclear Theory for Fast Neutron Data Evaluation held in Beijing 12-16 October 1987, as well as the conclusions and recommendations and the Chairman's summary of the meeting. The meeting presentations have been divided into six sessions devoted to the following topics: introductory speech (1 paper), optical potential (9 papers), compound nuclear theory (10 papers), pre-compound nuclear theory (13 papers), isomeric cross-section (1 paper) and intercomparison of nuclear model computer codes (1 paper). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  7. 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)

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

    International Nuclear Information System (INIS)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D.

    2011-01-01

    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)

  9. Evaluation of nuclear data of 244Pu and 237Pu

    International Nuclear Information System (INIS)

    Nakagawa, Tsuneo; Konshin, V.A.

    1995-10-01

    The evaluation of nuclear data for 244 Pu and 237 Pu was made in the neutron energy region from 10 -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 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)

  10. Effects of existing evaluated nuclear data files on neutronics characteristics of the BFS-62-3A critical assembly benchmark model

    International Nuclear Information System (INIS)

    Semenov, Mikhail

    2002-11-01

    This report is continuation of studying of the experiments performed on BFS-62-3A critical assembly in Russia. The objective of work is definition of the cross section uncertainties on reactor neutronics parameters as applied to the hybrid core of the BN-600 reactor of Beloyarskaya NPP. Two-dimensional benchmark model of BFS-62-3A was created specially for these purposes and experimental values were reduced to it. Benchmark characteristics for this assembly are 1) criticality; 2) central fission rate ratios (spectral indices); and 3) fission rate distributions in stainless steel reflector. The effects of nuclear data libraries have been studied by comparing the results calculated using available modern data libraries - ENDF/B-V, ENDF/B-VI, ENDF/B-VI-PT, JENDL-3.2 and ABBN-93. All results were computed by Monte Carlo method with the continuous energy cross-sections. The checking of the cross sections of major isotopes on wide benchmark criticality collection was made. It was shown that ENDF/B-V data underestimate the criticality of fast reactor systems up to 2% Δk. As for the rest data, the difference between each other in criticality for BFS-62-3A is around 0.6% Δk. However, taking into account the results obtained for other fast reactor benchmarks (and steel-reflected also), it may conclude that the difference in criticality calculation results can achieve 1% Δk. This value is in a good agreement with cross section uncertainty evaluated for BN-600 hybrid core (±0.6% Δk). This work is related to the JNC-IPPE Collaboration on Experimental Investigation of Excess Weapons Grade Pu Disposition in BN-600 Reactor Using BFS-2 Facility. (author)

  11. JEF-2.2. The evaluated neutron nuclear data library of the NEA Data Bank. Summary of contents

    International Nuclear Information System (INIS)

    Lemmel, H.D.; Schwerer, O.

    1996-01-01

    This document summarizes the contents of JEF-2.2, the Joint Evaluated File of neutron nuclear data compiled by the OECD Nuclear Energy Agency Data Bank, finalized in 1992 and released in 1993. The entire library or retrievals of selected materials are available from the IAEA Nuclear Data Section free of charge, either on magnetic tape, or online from NDIS, the interactive Nuclear Data Information System. (author)

  12. New software tools for evaluating and disseminating nuclear data

    International Nuclear Information System (INIS)

    Langlands, Tracy L.M.; Miyake, Erik E.; Stone, Craig A.

    2001-01-01

    Three new related technologies that offer real promise for modeling, processing, and disseminating nuclear data are explored. Extensible Markup Language (XML) provides a simple method of describing nuclear data. Extensible Style Language (XSL) supports XML data searching, filtering and processing. It is shown how the technology can be used to transform an XML-formatted ENSDF file into a table of similar form to those found in the Nuclear Data Sheets. Scalable Vector Graphics (SVG) has been used to convert XML formatted ENSDF files into interactive level scheme

  13. New nuclear data evaluations for Ca and Sc isotopes

    International Nuclear Information System (INIS)

    Koning, Arjan; Duijvestijn, Marieke

    2007-01-01

    New ENDF-6 formatted nuclear data libraries are presented for 40,42,43,44,46,48 Ca and 45 Sc, for incident neutrons and protons. Apart from the resonance range, which we have adopted from the best available source in existing libraries, the nuclear data evaluations are completely revised in the 0-20MeV energy range, and, moreover, extend up to 200 MeV. This collection of isotopic evaluations is created by using the nuclear model code TALYS with a consistent set of input parameters for all isotopes. The most important nuclear reaction models needed for our data files are described. We have intended to make these evaluations complete in their description of reaction channels and use a consistent method to store the data in ENDF-6 format, which include cross sections, angular distributions, double-differential spectra, discrete and continuum photon production cross sections, and residual production (activation) cross sections including isomers. It is shown that the data present in our libraries give an improved agreement with the existing basic experimental data. (author)

  14. FENDL-3.0: Processing the Evaluated Nuclear Data Library for Fusion Applications

    International Nuclear Information System (INIS)

    Lopez Aldama, D.; Noy, R. Capote

    2011-12-01

    A description of the work undertaken towards the development of a new version of the neutron-induced part of the Fusion Evaluated Nuclear Data Library (FENDL) for applications is summarized. The main issues related to the selection and processing of evaluated nuclear data files using the NJOY-99 and PREPRO-2010 processing systems are described. The new version of FENDL for applications, termed FENDL-3.0, includes the evaluated nuclear data files in ENDF-6 format, the continuous-energy cross section files in ACE format for the MCNP family of Monte Carlo codes and the multi-group data library in MATXS format for deterministic transport calculations up to 55 MeV for 180 isotopes. Further, additional data are supplied in GENDF format for sensitivity studies. The library is freely available from the Nuclear Data Section at the International Atomic Energy Agency. (author)

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

    International Nuclear Information System (INIS)

    Aoyama, Shigeyoshi; Ohbayasi, Yosihide; Masui, Hiroshi; Chiba, Masaki; Kato, Kiyoshi; Ohnishi, Akira

    2000-01-01

    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)

  16. Nuclear data services of the Nuclear Data Centers Network available at the National Nuclear Data Center

    International Nuclear Information System (INIS)

    McLane, V.

    1997-01-01

    The Nuclear Data Centers Network provides low and medium energy nuclear reaction data to users around the world. Online retrievals are available through the U.S. National Nuclear Data Center, the Nuclear Energy Agency Data Bank, and the IAEA Nuclear Data Section from these extensive bibliographic, experimental data, and evaluated data files. In addition to nuclear reaction data, the various databases also provide nuclear structure and decay data, and other information of interest to users. The WorldWideWeb sites at the National Nuclear Data Center and the NEA Data Bank provide access to some of the Centers' files. (orig.)

  17. Nuclear data project evaluation activity report. October 1998 - October 2000

    International Nuclear Information System (INIS)

    Akovali, Y.; Blackmon, J.; Radford, D.; Smith, M.

    2001-01-01

    This report summarizes the activities of the ORNL Nuclear Data Project since the IAEA Advisory Group meeting in December 1998. The group's future plans are also included. The ORNL Nuclear Data Project's responsibility includes the compilation/evaluation of astrophysics data, as well as the evaluation and compilation of nuclear structure data. The Nuclear Data Project, therefore, is composed of two groups. The Nuclear Data Project staff through September 2000 is listed below. Accomplishments for the period of October 1998 through September 2000 of the nuclear structure data group and the nuclear astrophysics group are submitted in this Nuclear Data Project report

  18. Nuclear data project evaluation activity report. October 1998 - October 2000

    Energy Technology Data Exchange (ETDEWEB)

    Akovali, Y; Blackmon, J; Radford, D; Smith, M [Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    2001-02-01

    This report summarizes the activities of the ORNL Nuclear Data Project since the IAEA Advisory Group meeting in December 1998. The group's future plans are also included. The ORNL Nuclear Data Project's responsibility includes the compilation/evaluation of astrophysics data, as well as the evaluation and compilation of nuclear structure data. The Nuclear Data Project, therefore, is composed of two groups. The Nuclear Data Project staff through September 2000 is listed below. Accomplishments for the period of October 1998 through September 2000 of the nuclear structure data group and the nuclear astrophysics group are submitted in this Nuclear Data Project report.

  19. Japanese evaluated nuclear data library, version-3 - JENDL-3

    International Nuclear Information System (INIS)

    Kikuchi, Yasuyuki

    1992-01-01

    The third version of Japanese Evaluated Nuclear Data Library (JENDL-3) has been developed aiming at really general applications such as fission, fusion and shielding calculations. The general purpose file of JENDL-3 contains neutron nuclear data for 324 nuclides in the ENDF-5 format. In the JENDL-3 evaluation, much effort has been devoted to improve reliability of high-energy data for fusion application, which were not satisfactory in JENDL-2, and to include gamma-ray production data. Some advanced nuclear theoretical models were adopted and recent experimental data of energy-angle double-differential cross sections (DDX) mainly measured in Japan were taken into account. Various benchmark tests have so far been made in order to verify the applicability of JENDL-3 to various fields. For fast reactor calculations, JENDL-3 gives satisfactory results for most of characteristics. Particularly, space dependences of reaction rates, sodium void coefficients and control rod worths, which were significant with JENDL-2, nearly disappear. This suggests that the JENDL-3 data are well balanced. Satisfactory applicability has been also proved for the other field such as thermal reactor calculations, fusion neutronics, shielding and dosimetry. (orig.)

  20. Documentation for WIMSD-formatted libraries based on ENDF/B-VII.1 evaluated nuclear data files with extended actinide burn-up chains and cross section data up to 2000 K for fuel materials

    International Nuclear Information System (INIS)

    López Aldama, Daniel

    2014-11-01

    In the frame of WIMS Library Update Project the WIMSD-IAEA-69 and WIMSD-IAEA-172 libraries were prepared and made available at the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). The main libraries were prepared from different sources of evaluated nuclear data that were available before December 2003. Also others WIMSD libraries were prepared from the major evaluated nuclear data libraries and made available at http://www-nds.iaea.org/wimsd. During the last ten years new libraries have been prepared every time that a major version of an evaluated nuclear data library has been released, namely JEFF-3.1 and ENDF/B-VII.0. Recently, end-users have requested to extend the temperature ranges of fuel materials included in the libraries and also to extend the burn-up chains to higher actinides up to Cf-254. The inclusion of new structural materials, like bismuth, has been also considered. Therefore, new WIMSD-formatted libraries in the 69- and 172-energy structure have been prepared with more materials, extended actinides burn-up chains and higher temperatures in thermal and resonance range

  1. Major questions about derivation of variance-covariance information for nuclear data evaluations

    International Nuclear Information System (INIS)

    Peelle, R.W.

    1982-01-01

    The uncertainties in and correlations among some evaluated nuclear data are now evaluated to permit estimation of data-related uncertainties in the outputs of neutronic calculations and to focus data improvement efforts. Questions are discussed that arise in trying to obtain adequate numerical files of variance-covariance uncertainty information. These involve (1) discrepant data, (2) experimental data with incompletely reported uncertainties, (3) uncertainties in nuclear model results, (4) uncertainty data for the resonance regions and for angle and energy distributions, and (5) the role of integral data in nuclear data evaluation. The question also arises whether files of uncertainty data designed for technological applications can suffice to represent past knowledge in an evaluation that includes new data. Directions are indicated toward resolving these questions

  2. 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.

  3. Evaluation of Nuclear Data for Nuclear R and D Projects

    International Nuclear Information System (INIS)

    Chang, J. H.; Lee, Y. O.; Gil, C. S. and others

    2005-04-01

    Nuclear structure database, neutron data, charged particle data, and high energy service were improved and the libraries of WIMSD-5B, HELIOS, KASHIL-E6 were updated in response to the relevant users' requests. Measured resonance data, 19 nuclides for high burn-up fuel, isotopes for the thorium cycle were evaluated. Gamma production cross sections for underground resource exploration and for the development of in-core detector were also evaluated. The computer code system for theoretical model calculation was improved for the high energy nuclear data and, then applied to the evaluation for the accelerator and space applications. For the production of radioisotope, 'KAERI Charged Particle Cross Section Library' was published. Various libraries such as for MCNP4C, WIMSD-5, fast reactor, shielding, fission product burnup, and reactor benchmark were generated, and a code system for neutron and charged particle transport simulation was installed and their library production system was developed. Neutron capture cross sections were measured using facilities in Kyoto Univ. and TIT of Japan, and in Dubna, Russia. The TOF facility at PAL was upgraded and measurements were performed for 12 samples. Fast neutron measurement system was designed and built in the VDG facility, and its characteristics were also estimated

  4. A design study of the consolidated data bank for the evaluated nuclear data libraries

    International Nuclear Information System (INIS)

    Hasegawa, Akira

    1987-11-01

    A design study establishing a consolidated data bank covering almost all evaluated nuclear data libraries available in the world was made. Broad user requirements known as data consolidation, data independence and data protection are highly considered in the fundamental system design. To realize the system a sophisticated data structuring method for the data consolidation, a high level language for query facility and data protection methods for data security were developed. From the work a data bank named EDFSRS: Evaluated Data Files Storage and Retrieval System has been developed, which is an operational data base system for the evaluated nuclear data libraries compiled in the major three formats: ENDF/B, UKNDL and KEDAK. This system consists of more than fifteen independent programs and some 180 Mega-byte data files and index files (data-base) of the loaded data. It is designed to be operated in the on-line TSS (Time Sharing System) mode, so that users can get any information from their desk top terminals available in these major three formats. Equipped functions are very wide from data loading up to data retrieval, data calculations, data presentation in graphs, index book production and preparation of user accounts. The constructed system is a stand alone system with a characteristic of self-contained system for a data base system thus it gains high portability for the transplantation to other machines. This system is a reflection of user needs to consolidate data in secure, reliable way and to provide easy end-user access to these data. (author)

  5. Total cross-sections assessment of neutron reaction with stainless steel SUS-310 contained in various nuclear data files

    International Nuclear Information System (INIS)

    Suwoto

    2002-01-01

    The integral testing of neutron cross-sections for Stainless Steel SUS-310 contained in various nuclear data files have been performed. The shielding benchmark calculations for Stainless Steel SUS-310 has been analysed through ORNL-Broomstick Experiment calculation which performed by MAERKER, R.E. at ORNL - USA ( 1) . Assessment with JENDL-3.1, JENDL-3.2, ENDF/B-IV, ENDF/B-VI nuclear data files and data from GEEL have also been carried out. The overall calculation results SUS-310 show in a good agreement with the experimental data, although, underestimate results appear below 3 MeV for all nuclear data files. These underestimation tendencies clearly caused by presented of iron nuclide which more than half in Stainless Steel compound. The total neutron cross-sections of iron nuclide contained in various nuclear data files relatively lower on that energy ranges

  6. The joint evaluated file: a new nuclear library for reactor calculations

    International Nuclear Information System (INIS)

    Rowlands, J.L.; Tubbs, N.

    1986-01-01

    The Joint Evaluated File Project (JEF) was set up in 1982 to decide on the selection of evaluations and to plan the benchmark testing and future evaluation programme. A library, called JEF-1, has now been assembled and tested and is available to scientists in NEA Data Bank Member countries. It uses the ENDF/B-V format. Neutron interaction data are provided for some 300 nuclides. The ENDF/B-V Standards file has been adopted. For the remaining nuclides the data have been selected from recent American, Japanese and European evaluations, with only limited re-evaluations. New evaluations have been adopted for thermal scattering, fission product yields and radioactive decay data. The results of the benchmark testing of JEF-1 are considered satisfactory. The programme of re-evaluation work to develop an improved library, JEF-2, is now in progress. This also involves more sophisticated benchmark testing, concentrating on data for the primary actinides and structural materials. (author)

  7. Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, May 2015

    International Nuclear Information System (INIS)

    Wang, Wenming; Yokoyama, Kenji; Kim, Do Heon; Kodeli, Ivan-Alexander; Hursin, Mathieu; Pelloni, Sandro; Palmiotti, Giuseppe; Salvatores, Massimo; Touran, Nicholas; Cabellos De Francisco, Oscar; )

    2015-05-01

    The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the fourth Subgroup meeting, held at the NEA, Issy-les-Moulineaux, France, on 19-20 May 2015. It comprises a Summary Record of the meeting, two papers on deliverables and all the available presentations (slides) given by the participants: 1 - Status of Deliverables: '1. Methodology' (K. Yokoyama); 2 - Status of Deliverables: '2. Comments on covariance data' (K. Yokoyama); 3 - PROTEUS HCLWR Experiments (M. Hursin); 4 - Preliminary UQ Efforts for TWR Design (N. Touran); 5 - Potential use of beta-eff and other benchmark for adjustment (I. Kodeli); 6 - k_e_f_f uncertainties for a simple case of Am"2"4"1 using different codes and evaluated files (I. Kodeli); 7 - k_e_f_f uncertainties for a simple case of Am"2"4"1 using TSUNAMI (O. Cabellos); 8 - REWIND: Ranking Experiments by Weighting to Improve Nuclear Data (G. Palmiotti); 9 - Recent analysis on NUDUNA/MOCABA applications to reactor physics parameters (E. Castro); 10 - INL exploratory study for SEG (A. Hummel); 11 - The Development of Nuclear Data Adjustment Code at CNDC (H. Wu); 12 - SG39 Perspectives (M. Salvatores). A list of issues and actions conclude the document

  8. 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)

  9. Nuclear data standards - International Evaluation Co-operation volume 7

    International Nuclear Information System (INIS)

    Carlson, A.D.; Shibata, K.; Vonach, H.; Hambsch, F.J.; Chen, Z.; Hofmann, H.M.; Oh, S.Y.; Badikov, S.A.; Gai, E.V.; Pronyaev, V.G.; Smith, D.L.; Hale, G.M.; Kawano, T.; Larson, N.M.

    2006-01-01

    A Working Party on International Evaluation Co-operation was established under the sponsorship of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data evaluations, validation and related topics. Its aim is also to provide a framework for co-operative activities between members of the major nuclear data evaluation projects. This includes the possible exchange of scientists in order to encourage co-operation. Requirements for experimental data resulting from this activity are compiled. The working party determines common criteria for evaluated nuclear data files with a view to assessing and improving the quality and completeness of evaluated data. The parties to the project are: ENDF (United States), JEFF/EFF (NEA Data Bank member countries) and JENDL (Japan). Co-operation with evaluation projects of non-OECD countries is organised through the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report was issued by Subgroup 7, which was in charge of producing new evaluated neutron cross-section standards. When starting the project, there was a general consensus on the need to update these standards, as significant improvements had been made to the experimental database since 1991 when the last evaluation of these standards was performed. The present work was accomplished through efficient collaboration between a task force of the US Cross-section Evaluation Working Group (CSEWG), a Co-ordinated Research Project (CRP) of the International Atomic Energy Agency (IAEA) and Subgroup 7 of the Working Party on International Evaluation Co-operation (WPEC) of the NEA Nuclear Science Committee. Work is reported on the results of an international effort to evaluate the neutron cross-section standards. The evaluations include the H(n,n), 6 Li(n,t), 10 B(n,α), 10 B(n,α1γ), 197 Au(n,γ), 235 U(n,f) and 238 U(n,f) standard reactions. Evaluations were also produced for the non-standard 238 U(n,γ) and 239 Pu

  10. Compilations and evaluations of nuclear structure and decay data

    International Nuclear Information System (INIS)

    Lorenz, A.

    1977-03-01

    This is the second issue of a report series on published and to-be-published compilations and evaluations of nuclear structure and decay (NSD) data. This compilation of compilations and evaluations is designed to keep the nuclear scientific community informed of the availability of compiled or evaluated NSD data, and contains references to laboratory reports, journal articles and books containing selected compilations and evaluations. It excludes references to ''mass-chain'' evaluations normally published in the ''Nuclear Data Sheets'' and ''Nuclear Physics''. The material contained in this compilation is sorted according to eight subject categories: general compilations; basic isotopic properties; nuclear structure properties; nuclear decay processes; half-lives, energies and spectra; nuclear decay processes: gamma-rays; nuclear decay processes: fission products; nuclear decay processes: (others); atomic processes

  11. Compilations and evaluations of nuclear structure and decay data

    International Nuclear Information System (INIS)

    Lorenz, A.

    1977-10-01

    This is the third issue of a report series on published and to-be-published compilations and evaluations of nuclear structure and decay (NSD) data. This compilation is published and distributed by the IAEA Nuclear Data Section approximately every six months. This compilation of compilations and evaluations is designed to keep the nuclear scientific community informed of the availability of compiled or evaluated NSD data, and contains references to laboratory reports, journal articles and books containing selected compilations and evaluations

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

    International Nuclear Information System (INIS)

    Rochman, D.; Koning, A. J.

    2012-01-01

    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 239 Pu, 56 Fe, 28 Si and 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)

  13. Direct utilization of information from nuclear data files in Monte Carlo simulation of neutron and photon transport

    International Nuclear Information System (INIS)

    Androsenko, P.; Joloudov, D.; Kompaniyets, A.

    2001-01-01

    Questions, related to Monte-Carlo method for solution of neutron and photon transport equation, are discussed in the work concerned. Problems dealing with direct utilization of information from evaluated nuclear data files in run-time calculations are considered. ENDF-6 format libraries have been used for calculations. Approaches provided by the rules of ENDF-6 files 2, 3-6, 12-15, 23, 27 and algorithms for reconstruction of resolved and unresolved resonance region cross sections under preset energy are described. The comparison results of calculations made by NJOY and GRUCON programs and computed cross sections data are represented. Test computation data of neutron leakage spectra for spherical benchmark-experiments are also represented. (authors)

  14. International co-operation in nuclear data evaluation

    International Nuclear Information System (INIS)

    Nordborg, C.

    2003-01-01

    The NEA Working Party on International Nuclear Data Evaluation Co-operation serves as a forum for the exchange of information on required improvements to evaluated nuclear data libraries used in all nuclear application areas. The main objective is to identify the major discrepancies in existing evaluated data libraries and to resolve these discrepancies in specifically established expert groups. The long-term goal is to have converging evaluated data libraries. This co-operative effort is very successful. It has resolved a number of outstanding nuclear data problems and has issued 15 reports in support of the studies undertaken jointly. (author)

  15. FENDL-2.1: Update of an evaluated nuclear data library for fusion applications

    International Nuclear Information System (INIS)

    Lopez Aldama, D.; Trkov, A.

    2004-12-01

    A description of the work undertaken towards the development of a new version of the FENDL-2 library is given, detailing the selection of the evaluated nuclear data files, the processing performed and the resultant processed files. These include an updated version of the FENDL-2 library (termed FENDL-2.1), the corresponding ACE library for MCNP family of Monte Carlo codes, the MATXS library for deterministic transport codes and the ACEDOP package for Doppler broadening of the resolved resonance cross sections in the ACE files. (author)

  16. Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, December 2015

    International Nuclear Information System (INIS)

    Cabellos, Oscar; De Saint Jean, Cyrille; Hursin, Mathieu; Pelloni, Sandro; Ivanov, Evgeny; Kodeli, Ivan; Leconte, Pierre; Palmiotti, Giuseppe; Salvatores, Massimo; Sobes, Vladimir; Yokoyama, Kenji

    2015-12-01

    The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the fifth formal Subgroup 39 meeting held at the Institute Curie, Paris, France, on 4 December 2015. It comprises a Summary Record of the meeting, and all the available presentations (slides) given by the participants: A - Sensitivity methods: - 1: Short update on deliverables (K. Yokoyama); - 2: Does one shot Bayesian is equivalent to successive update? Bayesian inference: some matrix linear algebra (C. De Saint Jean); - 3: Progress in Methodology (G. Palmiotti); - SG39-3: Use of PIA approach. Possible application to neutron propagation experiments (S. Pelloni); - 4: Update on sensitivity coefficient methods (E. Ivanov); - 5: Stress test for U-235 fission (H. Wu); - 6: Methods and approaches development at ORNL for providing feedback from integral benchmark experiments for improvement of nuclear data files (V. Sobes); B - Integral experiments: - 7a: Update on SEG analysis (G. Palmiotti); - 7b:Status of MANTRA (G. Palmiotti); - 7c: Possible new experiments at NRAD (G. Palmiotti); - 8: B-eff experiments (I. Kodeli); - 9: On going CEA activities related to dedicated integral experiments for nuclear date validation in the Fast energy range (P. Leconte); - 10: PROTEUS Experiments: an update (M. Hursin); - 11: Short updates on neutron propagation experiments, STEK, CIELO status (O. Cabellos)

  17. Evaluation of nuclear data for neutron dosimetry

    International Nuclear Information System (INIS)

    Tardelli, Tiago Cardoso

    2013-01-01

    Absorbed dose and Effective dose are usually calculated using radiation transport computer codes. The quality of the calculations of absorbed dose depends on nuclear data utilized, however, there are rare information about the differences in dose caused by the use of different libraries. The objective of this study is to compare dose values obtained using different nuclear data libraries due to external source of neutrons in the energy range from 10-11 to 20 MeV. The nuclear data libraries used are: JENDL 4.0, JEFF 3.3.1 and ENDF/B.VII. Dose calculations were carried out with the MCNPX code considering the anthropomorphic ICRP 110 model. The differences in the absorbed dose values using JEFF 3.3.1 and ENDF/B.VII libraries are small, around 1%, but the results obtained with JENDL 4.0 presented differences up to 85% compared to ENDF and JEFF results. Differences in effective dose values are around 1.5% between ENDF and JEFF and 11% between ENDF/B.VII and JENDL 4.0. (author)

  18. Introduction to the content of the major available evaluated nuclear data libraries

    International Nuclear Information System (INIS)

    Salvatores, M.

    1984-01-01

    The following notes were intended as complement to the main topic of the lectures presented at the Winter College of Nuclear Physics and Reactors. Actually, the topic was covered according to the outline given in Appendix and the presentation was based as far as possible on the practical features of the basic data files, in particular the ENDF/B files. The present notes are subdivided in two parts: part I is a general introduction to the problem of the evaluated data files and gives the main references on the topic. Part II presents a few specific examples of the use of the evaluated data files in the wide application fields of neutron heating a photon production. (author)

  19. Data Analysis of Minima Total Cross-sections of Nitrogen-14 on JENDL-3.2Nuclear Data File

    International Nuclear Information System (INIS)

    Suwoto; Pandiangan, Tumpal; Ferhat-Aziz

    2000-01-01

    The integral tests of neutron cross-section for shielding material suchas nitrogen-14 contained in JENDL-3.2 file have been performed. Analysis ofthe calculation for nitrogen-14 was based on the MAEKER's ORNL-BroomstickExperiment at ORNL-USA. For the data comparison, the calculation analysiswith JENDL-3.1 file, ENDF/B-IV file, ENDF/B-VI file and JEF2.2 have also beencarried out. The overall calculation results by using JENDL-3.2 evaluationshowed good agreement with the experimental data, as well as those with theENDF/B-VI evaluation. In particular, the JENDL-3.2 evaluation gave betterresults than JENDL-3.1 evaluation and ENDF/B-IV. It was been concluded thatthe total cross-sections of Nitrogen-14 contained in JENDL-3.2 file is invery good agreement with the experimental results, although the totalcross-section in the energy range between 0.5 MeV and 0.9 MeV on fileJENDL-3.2 was small (about 4% lower), and minima of total cross-sections wasdeeper. (author)

  20. Compilations and evaluations of nuclear structure and decay data

    International Nuclear Information System (INIS)

    Lorenz, A.

    1978-10-01

    This is the fourth issue of a report series on published and to-be-published compilations and evaluations of nuclear structure and decay (NSD) data. This compilation is published and distributed by the IAEA Nuclear Data Section every year. The material contained in this compilation is sorted according to eight subject categories: General compilations; basic isotopic properties; nuclear structure properties; nuclear decay processes, half-lives, energies and spectra; nuclear decay processes, gamma-rays; nuclear decay processes, fission products; nuclear decay processes (others); atomic processes

  1. Processing of evaluated neutron data files in ENDF format on personal computers

    International Nuclear Information System (INIS)

    Vertes, P.

    1991-11-01

    A computer code package - FDMXPC - has been developed for processing evaluated data files in ENDF format. The earlier version of this package is supplemented with modules performing calculations using Reich-Moore and Adler-Adler resonance parameters. The processing of evaluated neutron data files by personal computers requires special programming considerations outlined in this report. The scope of the FDMXPC program system is demonstrated by means of numerical examples. (author). 5 refs, 4 figs, 4 tabs

  2. Nuclear Structure References (NSR) file

    International Nuclear Information System (INIS)

    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

  3. Nuclear data for nuclear reactor analyses

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1984-01-01

    A discussion of nuclear data is presented emphasizing to what extent data are known and to what accuracy. The principal data of interest is that for neutron cross-sections. The changing status of data, evaluated nuclear data files and data validation and improvement are described. Although the discussion relates to nuclear data for reactor analysis may of the results also apply to fusion, accelerator, shielding, biomedical, space and defense studies. (U.K.)

  4. Program of evaluations for nuclear data centers

    International Nuclear Information System (INIS)

    Cunha Menezes Filho, A. da.

    1980-01-01

    Standard problems for evaluating basic data libraries of multigroup constant generation, and codes for calculating integral parameters existing or will exist in the near future in the advanced study division (EAV), are defined. (M.C.K.) [pt

  5. Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, November 2013

    International Nuclear Information System (INIS)

    De Saint Jean, C.; Dupont, E.; ); Dyrda, J.; Hursin, M.; Pelloni, S.; Ishikawa, M.; Ivanov, E.; Ivanova, T.; Kim, D.H.; Ee, Y.O.; Kodeli, I.; Leal, L.; Leichtle, D.; Palmiotti, G.; Salvatores, M.; Pronyaev, V.; Simakov, S.; )

    2013-11-01

    The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the first formal Subgroup 39 meeting held at the NEA, Issy-les-Moulineaux, France, on 28-29 November 2013. It comprises a Summary Record of the meeting and all the available presentations (slides) given by the participants: A - Recent data adjustments performances and trends: 1 - Recommendations from ADJ2010 adjustment (M. Ishikawa); 2 - Feedback on CIELO isotopes from ENDF/B-VII.0 adjustment (G. Palmiotti); 3 - Sensitivity and uncertainty results on FLATTOP-Pu (I. Kodeli); 4 - SG33 benchmark: Comparative adjustment results (S. Pelloni) 5 - Integral benchmarks for data assimilation: selection of a consistent set and establishment of integral correlations (E. Ivanov); 6 - PROTEUS experimental data (M. Hursin); 7 - Additional information on High Conversion Light Water Reactor (HCLWR aka FDWR-II) experiments (14 January 2014); 8 - Data assimilation of benchmark experiments for homogenous thermal/epithermal uranium systems (J. Dyrda); B - Methodology issues: 1 - Adjustment methodology issues (G. Palmiotti); 2 - Marginalisation, methodology issues and nuclear data parameter adjustment (C. De Saint Jean); 3 - Nuclear data parameter adjustment (G. Palmiotti). A list of issues and actions conclude the document

  6. 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

  7. New perspective in covariance evaluation for nuclear data

    International Nuclear Information System (INIS)

    Kanda, Y.

    1992-01-01

    Methods of nuclear data evaluation have been highly developed during the past decade, especially after introducing the concept of covariance. This makes it utmost important how to evaluate covariance matrices for nuclear data. It can be said that covariance evaluation is just the nuclear data evaluation, because the covariance matrix has quantitatively decisive function in current evaluation methods. The covariance primarily represents experimental uncertainties. However, correlation of individual uncertainties between different data must be taken into account and it can not be conducted without detailed physical considerations on experimental conditions. This procedure depends on the evaluator and the estimated covariance does also. The mathematical properties of the covariance have been intensively discussed. Their physical properties should be studied to apply it to the nuclear data evaluation, and then, in this report, are reviewed to give the base for further development of the covariance application. (orig.)

  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. The aims and activities of the International Network of Nuclear Structure and Decay Data Evaluators

    International Nuclear Information System (INIS)

    Nichols, A.L.; Tuli, J.K.

    2008-01-01

    The International Network of Nuclear Structure and Decay Data (NSDD) experts consists of a number of evaluation groups and data service centres 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 centres 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 experts to participate in NSDD activities. The technical contents of these NSDD workshops are described, along with the rationale for the inclusion of various topics. (authors)

  10. Evaluation of nuclear data and their uncertainties

    International Nuclear Information System (INIS)

    Story, J.S.

    1984-01-01

    Some topics studied within the Winfrith Nuclear Data Group in recent years, and still of current importance, are briefly reviewed. Moderator cross-sections; criteria to be met for reactor applications are listed; thermal neutron scattering theory is summarized, with the approximations used to facilitate comutation; neutron age data test stringently the accuracy of epithermal cross-sections; a modification of the CFS effective range treatment for S-wave scatter by H is presented, and new calculations with up-to-date slow neutron scattering data are advocated. Use of multilevel resonance formalisms; the top bound resonance should be included explicitly in calculations; additive statistical terms are given to allow for ''distant'' negative and positive resonances, in both MLBW and R-M formalisms; formulae are presented for estimating R-M level shifts for 1>0 resonances. Resonance mean spacings; the Syson-Mehta optimum estimator is utilised in a method which up-dates the staircase plot. Resonances of 56 Fe have been resolved to approx. 800keV, over which range the level density for given Jπ should increase 2-fold; this variation is allowed for in the mean spacing calculations. Fission-product decay power; present status of integral data and summation calculations for 235 U and 239 Pu fissions is summarized, with a variety of intercomparisons including 239 Pu/ 235 U ratios. Data uncertainties are considered, but the sequence of data on GAMMAsub(γ) for the 27.8keV resonance of 56 Fe provided a cautionary example. (author)

  11. ENDL-1978. LLL evaluated Nuclear Data Library 1978

    International Nuclear Information System (INIS)

    1979-07-01

    The contents and documentation of the 1978 version of the Evaluated Nuclear Data Library of the Lawrence Livermore Laboratory, USA are summarized. The Library contains numerical neutron reaction data for 88 isotopes or elements

  12. Thermal lattice benchmarks for testing basic evaluated data files, developed with MCNP4B

    International Nuclear Information System (INIS)

    Maucec, M.; Glumac, B.

    1996-01-01

    The development of unit cell and full reactor core models of DIMPLE S01A and TRX-1 and TRX-2 benchmark experiments, using Monte Carlo computer code MCNP4B is presented. Nuclear data from ENDF/B-V and VI version of cross-section library were used in the calculations. In addition, a comparison to results obtained with the similar models and cross-section data from the EJ2-MCNPlib library (which is based upon the JEF-2.2 evaluation) developed in IRC Petten, Netherlands is presented. The results of the criticality calculation with ENDF/B-VI data library, and a comparison to results obtained using JEF-2.2 evaluation, confirm the MCNP4B full core model of a DIMPLE reactor as a good benchmark for testing basic evaluated data files. On the other hand, the criticality calculations results obtained using the TRX full core models show less agreement with experiment. It is obvious that without additional data about the TRX geometry, our TRX models are not suitable as Monte Carlo benchmarks. (author)

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

    International Nuclear Information System (INIS)

    Chadwick, M.B.; Oblozinsky, P.; Herman, M.

    2006-01-01

    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, based on experimental data and 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, 6 Li, 10 B, Au and for 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 evaluations up to 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; (10) New methods for uncertainties and covariances, together with covariance evaluations for some sample cases; and (11) New actinide fission energy deposition. 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 uranium thermal assemblies is removed; (b) The 238 U and 208 Pb reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good

  14. Chinese evaluated nuclear data library, version 2 (CENDL-2)

    International Nuclear Information System (INIS)

    Cai Dunjiu; Liang Qichang; Liu Tingjin

    1997-01-01

    A complete set of neutron nuclear data for 54 important nuclides from H to 249 Cf has been evaluated and recommended, with the incident neutron energy range from 10 -5 eV to 20 MeV. The main features for CEDNDL-2 are as follows: on the basis of CENDL-1, was carried out the renewal evaluations, extended the energy region, supplemented the data type of evaluations, and added the new evaluations; established the computerized nuclear data library according to the international standard format; improved and developed the related theoretical methods and technology for nuclear data calculations and evaluation processing; developed a complete set of the theoretical calculation codes with new ideas and our own distinguishing features; and formed a complete set of programs for nuclear data processing and benchmark testing. With new experimental data, careful evaluation analysis and theoretical calculations, the evaluations for partial nuclides have our own distinguishing features to give significant improvement compared to the existing world-wide advanced nuclear data libraries. Some evaluations have been adopted by other advanced libraries. The CENDL-2 has been released as one of the five main advanced evaluated nuclear data libraries for users in the world by International Atomic Energy Agency

  15. INDL/A IAEA Nuclear Data Library for evaluated neutron reaction data of actinides

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1982-05-01

    This Library contains evaluations performed by participants of the IAEA Coordinated Research Project on the Intercomparison of Evaluations of Actinide Neutron Nuclear Data. The data are available on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

  16. Summary report of the 3. research co-ordination meeting on development of reference input parameter library for nuclear model calculations of nuclear data (Phase 1: Starter File)

    International Nuclear Information System (INIS)

    Oblozinsky, P.

    1997-09-01

    The report contains the summary of the third and the last Research Co-ordination Meeting on ''Development of Reference Input Parameter Library for Nuclear Model Calculations of Nuclear Data (Phase I: Starter File)'', held at the ICTP, Trieste, Italy, from 26 to 29 May 1997. Details are given on the status of the Handbook and the Starter File - two major results of the project. (author)

  17. Data modeling and evaluation

    International Nuclear Information System (INIS)

    Bauge, E.; Hilaire, S.

    2006-01-01

    This lecture is devoted to the nuclear data evaluation process, during which the current knowledge (experimental or theoretical) of nuclear reactions is condensed and synthesised into a computer file (the evaluated data file) that application codes can process and use for simulation calculations. After an overview of the content of evaluated nuclear data files, we describe the different methods used for evaluating nuclear data. We specifically focus on the model based approach which we use to evaluate data in the continuum region. A few examples, coming from the day to day practice of data evaluation will illustrate this lecture. Finally, we will discuss the most likely perspectives for improvement of the evaluation process in the next decade. (author)

  18. Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, December 2016

    International Nuclear Information System (INIS)

    Cabellos, Oscar; ); PELLONI, Sandro; Ivanov, Evgeny; Sobes, Vladimir; Fukushima, M.; Yokoyama, Kenji; Palmiotti, Giuseppe; Kodeli, Ivo

    2016-12-01

    The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the eighth Subgroup 39 meeting, held at the OECD NEA, Boulogne-Billancourt, France, on 1-2 December 2016. It comprises all the available presentations (slides) given by the participants: A - Presentations: Welcome and actions review (Oscar CABELLOS); B - Methods: - Detailed comparison of Progressive Incremental Adjustment (PIA) sequence results involving adjustments of spectral indices and coolant density effects on the basis of the SG33 benchmark (Sandro PELLONI); - ND assessment alternatives: Validation matrix vs XS adjustment (Evgeny IVANOV); - Implementation of Resonance Parameter Sensitivity Coefficients Calculation in CE TSUNAMI-3D (Vladimir SOBES); C - Experiment analysis, sensitivity calculations and benchmarks: - Benchmark tests of ENDF/B-VIII.0 beta 1 using sodium void reactivity worth of FCA-XXVII-1 assembly (M. FUKUSHIMA, Kenji YOKOYAMA); D - Adjustments: - Cross-section adjustment based on JENDL-4.0 using new experiments on the basis of the SG33 benchmark (Kenji YOKOYAMA); - Comparison of adjustment trends with the Cielo evaluation (Sandro PELLONI); - Expanded adjustment in support of CIELO initiative (Giuseppe PALMIOTTI); - First preliminary results of the adjustment exercise using ASPIS Fe88 and SNEAK-7A/7B k_e_f_f and b_e_f_f benchmarks (Ivo KODELI); E - Future actions, deliverables: - Discussion on future of SG39 and possible new subgroup (Giuseppe PALMIOTTI); - WPEC sub-group proposal: Investigation of Covariance Data in

  19. Nuclear Science References as a Tool for Data Evaluation

    International Nuclear Information System (INIS)

    Winchell, D.F.

    2005-01-01

    For several decades, the Nuclear Science References database has been maintained as a tool for data evaluators and for the wider pure and applied research community. This contribution will describe the database and recent developments in web-based access

  20. Source list of nuclear data bibliographies, compilations, and evaluations

    International Nuclear Information System (INIS)

    Burrows, T.W.; Holden, N.E.

    1978-10-01

    To aid the user of nuclear data, many specialized bibliographies, compilations, and evaluations have been published. This document is an attempt to bring together a list of such publications with an indication of their availability and cost

  1. JENDL-3. The Japanese evaluated nuclear data library

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1992-01-01

    This document summarizes the contents of JENDL-3.1, the Japanese evaluated data library for neutron nuclear data, released in 1989 and revised in Dec. 1990. It also summarizes the JENDL-3 fission-products cross-section data library released in 1990. The entire library or retrievals of selected materials are available on magnetic tape from the IAEA Nuclear Data Section free of charge. (author)

  2. Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, May 2016

    International Nuclear Information System (INIS)

    Herman, Michal Wladyslaw; Cabellos De Francisco, Oscar; Beck, Bret; Ignatyuk, Anatoly V.; Palmiotti, Giuseppe; Grudzevich, Oleg T.; Salvatores, Massimo; Chadwick, Mark; Pelloni, Sandro; Diez De La Obra, Carlos Javier; Wu, Haicheng; Sobes, Vladimir; Rearden, Bradley T.; Yokoyama, Kenji; Hursin, Mathieu; Penttila, Heikki; Kodeli, Ivan-Alexander; Plevnik, Lucijan; Plompen, Arjan; Gabrielli, Fabrizio; Leal, Luiz Carlos; Aufiero, Manuele; Fiorito, Luca; Hummel, Andrew; Siefman, Daniel; Leconte, Pierre

    2016-05-01

    The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. WPEC subgroup 40-CIELO (Collaborative International Evaluated Library Organization) provides a new working paradigm to facilitate evaluated nuclear reaction data advances. It brings together experts from across the international nuclear reaction data community to identify and document discrepancies among existing evaluated data libraries, measured data, and model calculation interpretations, and aims to make progress in reconciling these discrepancies to create more accurate ENDF-formatted files. SG40-CIELO focusses on 6 important isotopes: "1H, "1"6O, "5"6Fe, "2"3"5","2"3"8U, "2"3"9Pu. This document is the proceedings of the seventh formal Subgroup 39 meeting and of the Joint SG39+SG40 Session held at the NEA, OECD Conference Center, Paris, France on 10-11 May 2016. It comprises a Summary Record of the meeting, and all the available presentations (slides) given by the participants: A - Welcome and actions review (Oscar CABELLOS); B - Methods: - XGPT: uncertainty propagation and data assimilation from continuous energy covariance matrix and resonance parameters covariances (Manuele AUFIERO); - Optimal experiment utilization (REWINDing PIA), (G. Palmiotti); C - Experiment analysis, sensitivity calculations and benchmarks: - Tripoli-4 analysis of SEG experiments (Andrew HUMMEL); - Tripoli-4 analysis of BERENICE experiments (P. DUFAY, Cyrille DE SAINT JEAN); - Preparation of sensitivities of k-eff, beta-eff and shielding benchmarks for adjustment exercise (Ivo KODELI); - SA and

  3. Workshop on nuclear structure and decay data evaluation. Summary report

    International Nuclear Information System (INIS)

    Pronyaev, V.G.; Nichols, A.L.

    2003-01-01

    A summary is given of the aims and contents of the Workshop on Nuclear Structure and Decay Data (NSDD) Evaluation, including the agenda, lists of participants and their presentations, general comments and recommendations. The 1-week workshop was organized by the IAEA Nuclear Data Section, and held in Vienna, Austria, from 18 to 22 November 2002. Workshop material, including participants' presentations, computer codes, manuals and other materials for NSDD evaluators, are freely available on CD-ROM on request. (author)

  4. Decay data evaluation project: Evaluation of 52Mn and 52mMn nuclear decay data

    Science.gov (United States)

    Luca, Aurelian

    2017-09-01

    All nuclear decay data within the 52Fe-52m,52Mn-52Cr decay chain have been evaluated at IFIN-HH, Romania, as part of an IAEA coordinated research project (F41029) and incorporated into the Decay Data Evaluation Project (DDEP). Both 52Fe and daughter 52Mn are two potentially promising radionuclides to be incorporated into suitable radiopharmaceuticals for PET and SPECT imaging. The decay data evaluation of 52Fe has previously been published and reported to the IAEA Nuclear Data Section. Equivalent DDEP evaluations for 52Mn and 52mMn have also been completed recently, and are presented in summary form below. These improved decay data sets have also been reported to the IAEA in detail, and are highly suitable in dose rate calculations for their application in nuclear medicine.

  5. Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, November 2014

    International Nuclear Information System (INIS)

    Aufiero, Manuele; Ivanov, Evgeny; Hoefer, Axel; Yokoyama, Kenji; Da Cruz, Dirceu Ferreira; KODELI, Ivan-Alexander; Hursin, Mathieu; Pelloni, Sandro; Palmiotti, Giuseppe; Salvatores, Massimo; Barnes, Andrew; Cabellos De Francisco, Oscar; ); Ivanova, Tatiana; )

    2014-11-01

    The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the third formal Subgroup meeting held at the NEA, Issy-les-Moulineaux, France, on 27-28 November 2014. It comprises a Summary Record of the meeting and all the available presentations (slides) given by the participants: A - Sensitivity methods: 1 - Perturbation/sensitivity calculations with Serpent (M. Aufiero); 2 - Comparison of deterministic and Monte Carlo sensitivity analysis of SNEAK-7A and FLATTOP-Pu Benchmarks (I. Kodeli); B - Integral experiments: 1 - PROTEUS experiments: selected experiments sensitivity profiles and availability, (M. Hursin, M. Salvatores - PROTEUS Experiments, HCLWR configurations); 2 - SINBAD Benchmark Database and FNS/JAEA Liquid Oxygen TOF Experiment Analysis (I. Kodeli); 3 - STEK experiment Opportunity for Validation of Fission Products Nuclear Data (D. Da Cruz); 4 - SEG (tailored adjoint flux shapes) (M. Savatores - comments) 5 - IPPE transmission experiments (Fe, 238 U) (T. Ivanova); 6 - RPI semi-integral (Fe, 238 U) (G. Palmiotti - comments); 7 - New experiments, e.g. in connection with the new NSC Expert Group on 'Improvement of Integral Experiments Data for Minor Actinide Management' (G. Palmiotti - Some comments from the Expert Group) 8 - Additional PSI adjustment studies accounting for nonlinearity (S. Pelloni); 9 - Adjustment methodology issues (G. Palmiotti); C - Am-241 and fission product issues: 1 - Am-241 validation for criticality-safety calculations (A. Barnes - Visio

  6. Large scale Bayesian nuclear data evaluation with consistent model defects

    International Nuclear Information System (INIS)

    Schnabel, G

    2015-01-01

    The aim of nuclear data evaluation is the reliable determination of cross sections and related quantities of the atomic nuclei. To this end, evaluation methods are applied which combine the information of experiments with the results of model calculations. The evaluated observables with their associated uncertainties and correlations are assembled into data sets, which are required for the development of novel nuclear facilities, such as fusion reactors for energy supply, and accelerator driven systems for nuclear waste incineration. The efficiency and safety of such future facilities is dependent on the quality of these data sets and thus also on the reliability of the applied evaluation methods. This work investigated the performance of the majority of available evaluation methods in two scenarios. The study indicated the importance of an essential component in these methods, which is the frequently ignored deficiency of nuclear models. Usually, nuclear models are based on approximations and thus their predictions may deviate from reliable experimental data. As demonstrated in this thesis, the neglect of this possibility in evaluation methods can lead to estimates of observables which are inconsistent with experimental data. Due to this finding, an extension of Bayesian evaluation methods is proposed to take into account the deficiency of the nuclear models. The deficiency is modeled as a random function in terms of a Gaussian process and combined with the model prediction. This novel formulation conserves sum rules and allows to explicitly estimate the magnitude of model deficiency. Both features are missing in available evaluation methods so far. Furthermore, two improvements of existing methods have been developed in the course of this thesis. The first improvement concerns methods relying on Monte Carlo sampling. A Metropolis-Hastings scheme with a specific proposal distribution is suggested, which proved to be more efficient in the studied scenarios than the

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

    International Nuclear Information System (INIS)

    Nichols, Alan L.; Dimitrious, P.; Kondev, F. G.; Ricard-McCutchan, E.

    2015-01-01

    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.

  8. 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.

  9. 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.

  10. Evaluated neutronic file for indium

    International Nuclear Information System (INIS)

    Smith, A.B.; Chiba, S.; Smith, D.L.; Meadows, J.W.; Guenther, P.T.; Lawson, R.D.; Howerton, R.J.

    1990-01-01

    A comprehensive evaluated neutronic data file for elemental indium is documented. This file, extending from 10 -5 eV to 20 MeV, is presented in the ENDF/B-VI format, and contains all neutron-induced processes necessary for the vast majority of neutronic applications. In addition, an evaluation of the 115 In(n,n') 116m In dosimetry reaction is presented as a separate file. Attention is given in quantitative values, with corresponding uncertainty information. These files have been submitted for consideration as a part of the ENDF/B-VI national evaluated-file system. 144 refs., 10 figs., 4 tabs

  11. 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

  12. Integrated system for production of neutronics and photonics calculational constants. Program SIGMA1 (Version 77-1): Doppler broaden evaluated cross sections in the Evaluated Nuclear Data File/Version B (ENDF/B) format

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1977-01-01

    A code, SIGMA1, has been designed to Doppler broaden evaluated cross sections in the ENDF/B format. The code can only be applied to tabulated data that vary linearly in energy and cross section between tabulated points. This report describes the methods used in the code and serves as a user's guide to the code

  13. Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, May 2014

    International Nuclear Information System (INIS)

    Aliberti, G.; Archier, P.; Dunn, M.; Dupont, E.; Hill, I.; ); Garcia, A.; Hursin, M.; Pelloni, S.; Ivanova, T.; Kodeli, I.; Palmiotti, G.; Salvatores, M.; Touran, N.; Wenming, Wang; Yokoyama, K.

    2014-05-01

    The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the second Subgroup meeting, held at the NEA, Issy-les-Moulineaux, France, on 13 May 2014. It comprises a Summary Record of the meeting and all the available presentations (slides) given by the participants: A - Welcome: Review of actions (M. Salvatores); B - Inter-comparison of sensitivity coefficients: 1 - Sensitivity Computation with Monte Carlo Methods (T. Ivanova); 2 - Sensitivity analysis of FLATTOP-Pu (I. Kodeli); 3 - Sensitivity coefficients by means of SERPENT-2 (S. Pelloni); 4 - Demonstration - Database for ICSBEP (DICE) and Database and Analysis Tool for IRPhE (IDAT) (I. Hill); C - Specific new experiments: 1 - PROTEUS FDWR-II (HCLWR) program summary (M. Hursin); 2 - STEK and SEG Experiments, M. Salvatores 3 - Experiments related to "2"3"5U, "2"3"8U, "5"6Fe and "2"3Na, G. Palmiotti); 4 - Validation of Iron Cross Sections against ASPIS Experiments (JEF/DOC-420) (I. Kodeli); 5 - Benchmark analysis of Iron Cross-sections (EFFDOC-1221) (I. Kodeli 6 - Integral Beta-effective Measurements (K. Yokoyama on behalf of M. Ishikawa); D - Adjustment results: 1 - Impacts of Covariance Data and Interpretation of Adjustment Trends of ADJ2010, (K. Yokoyama); 2 - Revised Recommendations from ADJ2010 Adjustment (K. Yokoyama); 3 - Comparisons and Discussions on Adjustment trends from JEFF (CEA) (P. Archier); 4 - Feedback on CIELO Isotopes from ENDF/B-VII.0 Adjustment (G. Palmiotti); 5 - Demonstration - Plot comparisons of participants' results (E

  14. An evaluation of neutron nuclear data for natural lead

    International Nuclear Information System (INIS)

    Ma Gonggui; Zhou Yiming; Wang Shiming

    1990-04-01

    Complete neutron nuclear data for natural lead were evaluated based on both experimental data measured up to December 1985 and theoretical data calculated with program MUP2. The experimental data evaluation is mainly based on CENDL-1, except (n, 2n) cross section, for which there are newly measured data available. The data, in the neutron energy from 10 -5 eV to 20 MeV, contain cross section, angular distributions and energy spectra of secondary neutrons, and are in ENDF/B-4 format

  15. Coordination of the international network of nuclear structure and decay data evaluators. Summary report of an IAEA advisory group meeting

    International Nuclear Information System (INIS)

    Muir, D.W.; Pronyaev, V.G.

    1998-03-01

    The international network of nuclear structure and decay data (NSDD) evaluators aims at a complete and periodic nuclear structure and decay data evaluation of all nuclides, the continuous publication of these evaluations and their dissemination to the scientific community. The evaluated data resulting from this concerted international effort are introduced in the Evaluated Structure and Decay Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets. Periodic meetings of this network are held in order to maintain the coordination of all centres and groups participating in the compilation, evaluation and dissemination of NSDD, to maintain and improve the standards and rules governing NSDS evaluation, and to review the development and common use of the computerized systems and databases maintained specifically for this activity. This document is a summary report of the twelfth Meeting on the Coordination of the NSDD Evaluators held between 14-18 October 1996 in Budapest, Hungary

  16. Evaluated data collections from ENSDF

    International Nuclear Information System (INIS)

    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

  17. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Iwamoto, O., E-mail: iwamoto.osamu@jaea.go.jp; Iwamoto, N.; Kunieda, S.; Minato, F.; Shibata, K.

    2016-01-15

    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.

  19. Japanese evaluated nuclear data library version 3, JENDL-3

    International Nuclear Information System (INIS)

    Asami, Tetsuo; Igarashi, Shun-ichi; Ihara, Hitoshi

    1989-01-01

    The third version of Japanese Evaluated Nuclear Data Library, JENDL-3, has recently been compiled and issued. The major features of JENDL-3 are that it covers a much larger number of nuclides than the previous versions, that evaluation is made over the all energy regions from 10 -5 eV to 20 MeV using proper nuclear theories for each of the energy regions, and that it contains data on gamma ray generation. The present report first gives an outline of JENDL-3, and then describes the evaluation of nuclear data covering light nuclides, nuclides in structural materials, fission product nuclides, major actinide nuclides, transplutonium nuclides, and gamma ray generation. The applicability of JENDL-3 is examined through a variety of bench mark tests covering the fast reactor, thermal neutron reactor, shielding, neutronics of nuclear fusion reactor, dosimetry, and gamma ray generation data. The report also describes a library for calculation of decay heat, which has close relations with JENDL-3. It has been demonstrated that the experimental data given in this library are very reliable with high reproducibility. Additional activities planned for the future are also outlined briefly. (N.K.)

  20. File: nuclear safety and transparency

    International Nuclear Information System (INIS)

    Martinez, J.P.; Etchegoyen, A.; Jeandron, C.

    2001-01-01

    Several experiences of nuclear safety and transparency are related in this file. Public information, access to documents, transparency in nuclear regulation are such subjects developed in this debate. (N.C.)

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

    International Nuclear Information System (INIS)

    Fujiwara, D.; Kosaka, S.

    2008-01-01

    Criticality benchmark testing was performed with evaluated nuclear data libraries for thermal, low-enriched uranium fuel rod applications. C/E values for k 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 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)

  2. Comparison of WIMS results using libraries based on new evaluated data files

    International Nuclear Information System (INIS)

    Trkov, A.; Ganesan, S.; Zidi, T.

    1996-01-01

    A number of selected benchmark experiments have been modelled with the WIMS-D/4 lattice code. Calculations were performed using multigroup libraries generated from a number of newly released evaluated data files. Data processing was done with the NJOY91.38 code. Since the data processing methods were the same in all cases, the results may serve to determine the impact on integral parameters due to differences in the basic data. The calculated integral parameters were also compared to the measured values. Observed differences were small, which means that there are no essential differences between the evaluated data libraries. The results of the analysis cannot serve to discriminate in terms of quality of the data between the evaluated data libraries considered. For the test cases considered the results with the new, unadjusted libraries are at least as good as those obtained with the old, adjusted WIMS library which is supplied with the code. (author). 16 refs, 3 tabs

  3. 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).

  4. FOND-2.2-evaluated nuclear data library for constants sets generation at ABBN constants providing system

    International Nuclear Information System (INIS)

    Koscheev, V.N.; Nikolaev, M.N.; Tsiboulia, A.M.

    2002-01-01

    The library FOND-2.2 of evaluated nuclear data files, which was created at the ABBN laboratory of IPPE, is described. FOND-2 library is the basic nuclear data source used for the preparation of group data sets with different energy structures. ABBN-93.1 group data set was retrieved from the FOND-2 data library and nowadays it is widely used in different applications, in neutronics calculations of different nuclear energetic installations with different kinds of neutron spectra, in radiation shielding calculation, and so on. (author)

  5. Review of nuclear reaction data evaluation in the US

    Energy Technology Data Exchange (ETDEWEB)

    Howerton, R.J.

    1985-05-01

    The development of the nuclear reaction data evaluation activities in the US over the last 40 years is reviewed, starting with comments on several reports as early as 1944. The review moves on to the development of consortia to share the burden by interchanging sets of data and efforts toward putting together an encoding system and computer-oriented formats. It is predicted that future emphasis is likely to be on charged particle induced reactions. (LEW)

  6. Review of nuclear reaction data evaluation in the US

    International Nuclear Information System (INIS)

    Howerton, R.J.

    1985-05-01

    The development of the nuclear reaction data evaluation activities in the US over the last 40 years is reviewed, starting with comments on several reports as early as 1944. The review moves on to the development of consortia to share the burden by interchanging sets of data and efforts toward putting together an encoding system and computer-oriented formats. It is predicted that future emphasis is likely to be on charged particle induced reactions

  7. Evaluated nuclear data for Th-U fuel cycle. Summary report of the second research coordination meeting

    International Nuclear Information System (INIS)

    Schillebeeckx, P.; Trkov, A.

    2004-12-01

    Highlights of the second research coordination meeting are given with respect to progress, and the agreed route forward to achieve the primary objectives of the coordinated research project on 'Evaluated Nuclear data for Th-U Fuel Cycle'. Participants debated their findings and requirements for such files, and formulated a list of assigned tasks. (author)

  8. ENDF/B-VI nuclear data evaluations for fusion applications

    International Nuclear Information System (INIS)

    Dunford, C.L.; Larson, D.C.; Young, P.G.

    1988-01-01

    The next release of the ENDF/B data library planned for 1989 contains improved data evaluations of interest to the fusion neutronics community. New data formats permit inclusion of energy-angle correlated particle emission spectra and recoil nucleus energy spectra. Enhanced formats for covariance information have been developed. Many new isotopic evaluations will lead to improved energy conservation and kerma factor calculations. Improved nuclear model calculations will provide reliable particle emission data where experimental information is sparse. Improved Bayssian fitting codes will provide more accurate evaluations for data rich reactions such as Li(n,nt)α. All of the most important fusion material evaluations contain these new features. 32 refs., 8 figs

  9. Evaluation of neutron nuclear data for 249Cf

    International Nuclear Information System (INIS)

    Zhou Delin; Yu Baosheng; Yuan Hanrong; Liu Tong; Zhang Jin; Su Zongdi; Yan Shiwei; Wang Cuilan; Zhang Jingshang

    1992-01-01

    A complete set of neutron nuclear data from 10 -5 eV to 20 MeV in ENDF/B-6 format has been evaluated for 249 Cf based on measured data, systematics predications and model theory calculations. The evaluated quantities are the total, elastic and inelastic scattering, fission, capture, (n,2n), (n,3n) reaction cross sections, the resolved and unresolved resonance parameters, the angular and energy distributions of emitted neutrons and the average number of neutrons emitted per fission. The numerical data are available in ENDF/B-6 format

  10. Study of nuclear data online services

    International Nuclear Information System (INIS)

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

    2003-01-01

    A web-based nuclear data service software system, NDOS ( Nuclear Data Online Services), has been developed and released in Sep. 2001. Through the Internet, this system distributes charge of free 8 international nuclear databases: 5 evaluated neutron databases (BROND, CENDL, ENDF, JEF and, JENDL), Evaluated Nuclear Structure and Decay File ENSDF, Experimental Nuclear Data Library EXFOR database and IAEA Photonuclear Data Library. A software package, NDVS (Nuclear Data Viewing System), facilitates the visualization and manipulation of nuclear data. The computer programs providing support for database management and data retrievals are based on the Linux implementation of PHP and the MySQL software. (authors)

  11. Nuclear data for the high-spin community

    Energy Technology Data Exchange (ETDEWEB)

    Firestone, R B [Lawrence Berkeley Lab., CA (United States); Singh, B [McMaster Univ., Hamilton, ON (Canada). Tandem Accelerator Lab.

    1992-08-01

    The Isotopes Project at Berkeley is developing the Evaluated High-Spin Data File, a subset of the Evaluated Nuclear Structure Data File (ENSDF). The following products were under development at the time of the conference: eighth edition of the Table of Isotopes, electronic table of isotopes, data bases, nuclear charts, nuclear wallet cards, nuclear CD-ROM, FAX data services, on-line data services.

  12. Nuclear data evaluation at intermediate energies: An introduction

    International Nuclear Information System (INIS)

    Koning, A.J.

    2001-01-01

    An outline is presented of the status of nuclear data evaluation for intermediate energies. Our specific contribution to the field concerns neutron and proton transport data libraries, for energies below about 150 MeV. The evaluated data are calculated and stored in ENDF6-format with the computer codes ECIS96, GNASH and MINGUS. New phenomenological optical model potentials up to 200 MeV are presented and we illustrate the library production with a short outline of the other employed physical methods. The calculated results are compared with the available experimental data. A 68 MeV neutron transmission experiment on iron has been analyzed with MCNPX using the Los Alamos LA150 neutron data library, the ECN/BRC 150 MeV neutron data library and with the intranuclear cascade code LAHET. The clear improvement by using the data libraries is confirmed. (author)

  13. Investigation of knowledge structure of nuclear data evaluation code

    International Nuclear Information System (INIS)

    Uenaka, Junji; Kambayashi, Shaw

    1988-08-01

    In this report, investigation results of knowledge structure in a nuclear data evaluation code are described. This investigation is related to the natural language processing and the knowledge base in the research theme of Human Acts Simulation Program (HASP) begun at the Computing Center of JAERI in 1987. By using a machine translation system, an attempt has been made to extract a deep knowledge from Japanese sentences which are equivalent to a FORTRAN program CASTHY for nuclear data evaluation. With the knowledge extraction method used by the authors, the verification of knowledge is more difficult than that of the prototyping method in an ordinary AI technique. In the early stage of building up a knowledge base system, it seems effective to extract and examine knowledge fragments of limited objects. (author)

  14. Evaluation of neutron nuclear data for 12C

    International Nuclear Information System (INIS)

    Shibata, Keiichi

    1983-12-01

    Neutron nuclear data of 12 C have been evaluated for JENDL-3 in the energy range from 10 -5 eV to 20 MeV. Evaluated quantities are the total, elastic and inelastic scattering, radiative capture, photon-production, (n,p), (n,d) and (n,α) reaction cross sections and the angular or energy distribution of neutrons and photons. The total cross section below the threshold energy of the inelastic scattering has been calculated on the basis of the R-matrix theory. Three discrete levels have been taken into account for the inelastic scattering. (author)

  15. 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)

  16. The US Nuclear Data Network

    International Nuclear Information System (INIS)

    1993-01-01

    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

  17. 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.

  18. Formats and processing of evaluated nuclear data into multigroup cross-sections

    International Nuclear Information System (INIS)

    Motta, M.

    1984-01-01

    The first part of these lectures concerns the data in nuclear files and their manipulation. The structure of the data files as divided into the resonance region (subdivided into the resolved and the unresolved regions) and the continuum region is presented. The reactions concerned are the elastic scattering; the radiative capture and the fission methods for averaging the cross sections are given. Then, the group averaging formulas and the self-shielding factors are presented in some detail. The second part concerns a presentation of nuclear data files handling and conversion. The main libraries are listed and several maintenance computer codes presented. The way the conversion among different files is handled is also presented. The listings of several BASIC programs for different cross section calculations are given. These codes are self-guided

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

    International Nuclear Information System (INIS)

    Kimura, Itsuro

    2000-01-01

    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)

  20. NEA Data Bank progress report to the nuclear reaction data centres

    International Nuclear Information System (INIS)

    1988-01-01

    The report presents shortly the activities of the NEA Data Bank concerning neutron data compilation, the Joint Evaluated File, computer program services, validation of nuclear model codes, nuclear waste management and reactor safety

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

    International Nuclear Information System (INIS)

    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

  2. JEFF 3.1.2 - Joint evaluated nuclear data library for fission and fusion applications - February 2012 (DVD)

    International Nuclear Information System (INIS)

    2012-02-01

    The Joint Evaluated Fission and Fusion File (JEFF) project is a collaboration between NEA Data Bank member countries. The JEFF library combines the efforts of the JEFF and EFF/EAF Working Groups to produce a common sets of evaluated nuclear data, mainly for fission and fusion applications. The JEFF-3.1.2 version, released in February 2012, contains a number of different data types, including neutron and proton interaction data, radioactive decay data, fission yields, and thermal scattering law data. Currently, JEFF-3.1.2 data are available in ENDF-6 format (neutron library) from the Web. This new release is an update from JEFF-3.1.1 which concerns 115 material files from the general purpose incident neutron library which have been modified since JEFF-3.1.1. Modifications include: Hf isotopes: 6 new Hf evaluations have replaced previous ones; Gamma production data from neutron capture (MF=6 MT=102) has been added to 89 fission products (FP) evaluations; 47 of these FP have been replaced by ENDF-B/VII.0 evaluations, with gamma data added in this release. Corrections from JEFF-Beta feedback have been incorporated for 15 materials. Corrections that solve NJOY covariance processing problems and JANIS warnings have been made to 6 files. This DVD contains: - General purpose incident neutron data in ENDF-6 and ACE formats; - Activation data; - Thermal scattering data; - Incident proton data; - Radioactive decay data; - Neutron-induced fission yields data; - Spontaneous fission yields data

  3. Collection and evaluation of nuclear data of Th-232

    International Nuclear Information System (INIS)

    Osawa, Takaaki

    1979-01-01

    Present status of the requirement to and measurement and evaluation of the nuclear data of Th-232 is presented. The accuracy and energy range of the observed data at present are not enough to the demand from reactor engineering. The data of total cross-section are given in the energy range from 1.5 to 15 MeV from the data by Foster and Fasoli. The data by Uttley for the energy less than 1.5 MeV were accepted. Recently, Whalen and Kobayashi presented new data. Optical potential parameters were deduced. Re-normalization of the capture cross-sections of Th-232 was made on the basis of the evaluated values by Matsunobu and by Kanda. The values are a little smaller than the values in ENDF/B-4. Fission cross-sections were given by Henkel up to 9 MeV, and by Rago and Pankratov for the energy range above 9 MeV. Recently, Behrens presented new data for wide energy range. The accuracy of the measured cross-sections of inelastic scattering is not enough for reactor design. The accurate values of the cross-sections of (n, 2n) reaction of Th-232 have been demanded. Resonance parameters have been measured for wide energy range. In the energy range of thermal neutrons, the capture cross-section is about 7.4 barn. The characteristics of velocity dependence of the capture cross-section in this range should be investigated. (Kato, T.)

  4. Evaluation of sodium-23 neutron capture cross section data for the ENDF/B V-III file

    International Nuclear Information System (INIS)

    Paik, N.C.; Pitterle, T.A.

    1975-01-01

    The evaluation of neutron cross sections of 23 Na, material number 1156, for the ENDF/B File is described. Cross sections were evaluated between 10 -5 eV and 15 MeV. Experimental data available up to March 1971 were included in the evaluation

  5. Uncertainty-driven nuclear data evaluation including thermal (n,α) applied to 59Ni

    Science.gov (United States)

    Helgesson, P.; Sjöstrand, H.; Rochman, D.

    2017-11-01

    This paper presents a novel approach to the evaluation of nuclear data (ND), combining experimental data for thermal cross sections with resonance parameters and nuclear reaction modeling. The method involves sampling of various uncertain parameters, in particular uncertain components in experimental setups, and provides extensive covariance information, including consistent cross-channel correlations over the whole energy spectrum. The method is developed for, and applied to, 59Ni, but may be used as a whole, or in part, for other nuclides. 59Ni is particularly interesting since a substantial amount of 59Ni is produced in thermal nuclear reactors by neutron capture in 58Ni and since it has a non-threshold (n,α) cross section. Therefore, 59Ni gives a very important contribution to the helium production in stainless steel in a thermal reactor. However, current evaluated ND libraries contain old information for 59Ni, without any uncertainty information. The work includes a study of thermal cross section experiments and a novel combination of this experimental information, giving the full multivariate distribution of the thermal cross sections. In particular, the thermal (n,α) cross section is found to be 12.7 ± . 7 b. This is consistent with, but yet different from, current established values. Further, the distribution of thermal cross sections is combined with reported resonance parameters, and with TENDL-2015 data, to provide full random ENDF files; all of this is done in a novel way, keeping uncertainties and correlations in mind. The random files are also condensed into one single ENDF file with covariance information, which is now part of a beta version of JEFF 3.3. Finally, the random ENDF files have been processed and used in an MCNP model to study the helium production in stainless steel. The increase in the (n,α) rate due to 59Ni compared to fresh stainless steel is found to be a factor of 5.2 at a certain time in the reactor vessel, with a relative

  6. Evaluation of neutron nuclear data for 16O

    International Nuclear Information System (INIS)

    Shibata, Keiichi; Chiba, Satoshi; Nakajima, Yutaka; Asami, Tetsuo; Murata, Toru; Kanda, Yukinori; Tanaka, Shigeya.

    1990-02-01

    Neutron nuclear data of 16 O have been evaluated for JENDL-3 in the energy range from 10 -5 eV to 20 MeV. Evaluated quantities are the total, elastic and inelastic scattering, (n,2n), (n,γ), (n,p), (n,d), (n,α), (n,np) and (n,nα) reaction cross sections and the angular and energy distributions of emitted neutrons and gamma-rays. The total cross section below 3 MeV was calculated on the basis of the R-matrix theory. The inelastic scattering, (n,np) and (n,nα) reaction cross sections were obtained from the statistical model calculation. The gamma-ray production cross section was also calculated with the statistical model. (author)

  7. Evaluation of neutron nuclear data for 243Am

    International Nuclear Information System (INIS)

    Igarasi, Sin-iti; Nakagawa, Tsuneo

    1977-06-01

    Evaluation of neutron nuclear data for 243 Am was performed below 16 MeV. The energy region above 250 eV was separated from the lower region where the resonance parameters were given. Evaluation was made to select suitable resonance parameters, and thermal values of the capture and fission cross sections were obtained with the adopted resonance parameters. An average fission width was assumed to bridge the cross sections at 0.0253 eV and above 250 eV. Using a semi-empirical formula, the fission cross section was reproduced above 250 eV. Optical and statistical model calculations were made in order to obtain the total, capture, inelastic and elastic scattering, and (n,2n) reaction cross sections. (auth.)

  8. Activation cross section data file, (1)

    International Nuclear Information System (INIS)

    Yamamuro, Nobuhiro; Iijima, Shungo.

    1989-09-01

    To evaluate the radioisotope productions due to the neutron irradiation in fission of fusion reactors, the data for the activation cross sections ought to be provided. It is planning to file more than 2000 activation cross sections at final. In the current year, the neutron cross sections for 14 elements from Ni to W have been calculated and evaluated in the energy range 10 -5 to 20 MeV. The calculations with a simplified-input nuclear cross section calculation system SINCROS were described, and another method of evaluation which is consistent with the JENDL-3 were also mentioned. The results of cross section calculation are in good agreement with experimental data and they were stored in the file 8, 9 and 10 of ENDF/B format. (author)

  9. Proceedings of the Second international Workshop on Nuclear Data Evaluation for Reactor applications (Wonder 2009)

    International Nuclear Information System (INIS)

    2009-01-01

    The NEA (Nuclear Energy Agency) has collaborated with the CEA in the organization of the second international workshop on nuclear data evaluation for reactor applications: Wonder 2009. About 50 scientists have participated to the workshop and 38 presentations have been made, they have been organized around 4 sessions: 1) nuclear data measurements, 2) theory, modeling and evaluation of nuclear data, 3) uncertainties and covariance matrices, and 4) processing and validation of nuclear data

  10. Status and evaluation methods of JENDL fusion file and JENDL PKA/KERMA file

    International Nuclear Information System (INIS)

    Chiba, S.; Fukahori, T.; Shibata, K.; Yu Baosheng; Kosako, K.

    1997-01-01

    The status of evaluated nuclear data in the JENDL fusion file and PKA/KERMA file is presented. The JENDL fusion file was prepared in order to improve the quality of the JENDL-3.1 data especially on the double-differential cross sections (DDXs) of secondary neutrons and gamma-ray production cross sections, and to provide DDXs of secondary charged particles (p, d, t, 3 He and α-particle) for the calculation of PKA and KERMA factors. The JENDL fusion file contains evaluated data of 26 elements ranging from Li to Bi. The data in JENDL fusion file reproduce the measured data on neutron and charged-particle DDXs and also on gamma-ray production cross sections. Recoil spectra in PKA/KERMA file were calculated from secondary neutron and charged-particle DDXs contained in the fusion file with two-body reaction kinematics. The data in the JENDL fusion file and PKA/KERMA file were compiled in ENDF-6 format with an MF=6 option to store the DDX data. (orig.)

  11. Prototype of evaluation guidance system in Integrated Nuclear Data Evaluation System

    International Nuclear Information System (INIS)

    Fukahori, T.; Nakagawa, T.

    1992-01-01

    Integrated Nuclear Data Evaluation System (INDES) is being developed to keep experiences of nuclear data evaluation for JENDL-3 and to support new evaluations. One of the INDES functions is to set up input data of theoretical calculation codes automatically. In order to use INDES effectively, a prototype of nuclear data evaluation guidance system (E.T.; Evaluation Tutor) was made to help users in selecting a set of suitable theoretical calculation codes by applying knowledge engineering technology. E.T. consists of an inference engine, frames, a rule-base, two example-bases and calculating modules of certainty factors. The inference engine and the calculating modules are written in FORTRAN77. (author)

  12. Development of nuclear decay data library JDDL, and nuclear generation and decay calculation code COMRAD

    International Nuclear Information System (INIS)

    Naito, Yoshitaka; Ihara, Hitoshi; Katakura, Jun-ichi; Hara, Toshiharu.

    1986-08-01

    For safety evaluation of nuclear fuel facilities, a nuclear decay data library named JDDL and a computer code COMRAD have been developed to calculate isotopic composition of each nuclide, radiation source intensity, energy spectrum of γ-ray and neutron, and decay heat of spent fuel. JDDL has been produced mainly from the evaluated nuclear data file ENSDF to use new nuclear data. To supplement the data file for short life nuclides, the JNDC data set were also used which had been evaluated by Japan Nuclear Data Committee. Using these data, calculations became possible from short period to long period after irradiation. (author)

  13. Release of the 2008 Evaluated Nuclear Data Library (ENDL2008)

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D A; Descalle, M; Hoffman, R; Kelley, K; Navratil, P; Pruet, J; Summers, N; Thompson, I; Vogt, R

    2009-05-08

    Livermore's N-Division is now releasing the first version of a major new nuclear data library. This includes some 500 evaluations (roughly four times the number in the previous standard) and many physics improvements important for calculating weapon performance, output effects, attribution signatures, key radiochemical diagnostics and performance of conventional and hybrid fission/fusion reactors. As this library is more extensive and on a much firmer nuclear physics footing than the previous ENDL99 it should become, after a period of trial use by the applied community, the new standard for programmatic applications at Livermore. This work was supported by ASC-PEM and Campaign 4. Our basic philosophy in this release was to adopt the best work of the world's different nuclear data efforts. We have drawn heavily from the U.S. ENDF project (led by Brookhaven), the Japanese JENDL project (JAEA), and the European JEFF project (NEA). Because those efforts tend to focus on reactor applications they do not include an account of the charged particles emitted following a reaction. To enable broader applications we have used theory-based calculations to add a complete description of charged particles in all evaluations in the new library. This release also includes results from the last ten years of theory and experimental work here at Livermore. Some of the most important results include the surrogate campaign for unstable uranium isotopes, the LLNL/LANL 239Pu(n,2n) evaluation, the 241Am(n,2n) evaluation validated by the recent Livermore-led experiments, and measurements of 48Ti(n,2n). As well, we have adopted more than a hundred theory-based evaluations for radiochemical diagnostics completed by R. Hoffman and M. Mustafa and that use improved optical models, level densities, and decay scheme evaluations from the theory effort. These were extended to be transport complete (they now include a description of all of the particles emitted in reactions) to enable their

  14. Release of the 2008 Evaluated Nuclear Data Library (ENDL2008)

    International Nuclear Information System (INIS)

    Brown, D.A.; Descalle, M.; Hoffman, R.; Kelley, K.; Navratil, P.; Pruet, J.; Summers, N.; Thompson, I.; Vogt, R.

    2009-01-01

    Livermore's N-Division is now releasing the first version of a major new nuclear data library. This includes some 500 evaluations (roughly four times the number in the previous standard) and many physics improvements important for calculating weapon performance, output effects, attribution signatures, key radiochemical diagnostics and performance of conventional and hybrid fission/fusion reactors. As this library is more extensive and on a much firmer nuclear physics footing than the previous ENDL99 it should become, after a period of trial use by the applied community, the new standard for programmatic applications at Livermore. This work was supported by ASC-PEM and Campaign 4. Our basic philosophy in this release was to adopt the best work of the world's different nuclear data efforts. We have drawn heavily from the U.S. ENDF project (led by Brookhaven), the Japanese JENDL project (JAEA), and the European JEFF project (NEA). Because those efforts tend to focus on reactor applications they do not include an account of the charged particles emitted following a reaction. To enable broader applications we have used theory-based calculations to add a complete description of charged particles in all evaluations in the new library. This release also includes results from the last ten years of theory and experimental work here at Livermore. Some of the most important results include the surrogate campaign for unstable uranium isotopes, the LLNL/LANL 239Pu(n,2n) evaluation, the 241Am(n,2n) evaluation validated by the recent Livermore-led experiments, and measurements of 48Ti(n,2n). As well, we have adopted more than a hundred theory-based evaluations for radiochemical diagnostics completed by R. Hoffman and M. Mustafa and that use improved optical models, level densities, and decay scheme evaluations from the theory effort. These were extended to be transport complete (they now include a description of all of the particles emitted in reactions) to enable their use in

  15. UK Chemical Nuclear Data Committee progress report

    International Nuclear Information System (INIS)

    Nichols, A.L.

    1990-01-01

    Basic nuclear data requirements for industrial application are monitored by the UK Chemical Nuclear Data Committee (UKCNDC), covering half-lives, decay data, fission yields and the content of computerised data files. While the UKCNDC Request list was reviewed at the end of 1989 to reveal new and continued requirements, funding problems have increased during the year. Difficulties in the UK nuclear power industry are reflected in the decline in experimental studies, although evaluation efforts have been maintained. (author)

  16. IAEA Nuclear Data Section: Progress Report, 2010/11

    International Nuclear Information System (INIS)

    Simakov, S.P.; Otsuka, N.; Zerkin, V.; Semkova, V.

    2011-01-01

    Summary of Nuclear Data Activity by Staff of the IAEA Nuclear Data Section from April 2010 - May 2011 including Staff Changes, Data Compilations (EXFOR transmission, EXFOR quality control, EXFOR coverage control, Workshops and Meetings in 2010/2011 relevant to EXFOR, CINDA, Evaluated data libraries, files and programs), Services, software and Nuclear Data Developments

  17. On the covariance matrices in the evaluated nuclear data

    International Nuclear Information System (INIS)

    Corcuera, R.P.

    1983-05-01

    The implications of the uncertainties of nuclear data on reactor calculations are shown. The concept of variance, covariance and correlation are expressed first by intuitive definitions and then through statistical theory. The format of the covariance data for ENDF/B is explained and the formulas to obtain the multigroup covariances are given. (Author) [pt

  18. Evaluation of correlative nuclear data at certain energy point

    International Nuclear Information System (INIS)

    Zhang Jianhua; Liu Tingjin.

    1993-01-01

    A method to process correlative nuclear data at certain energy point is presented. The corresponding processing code has also been developed. Using the code, the effects of the correlation have been discussed in detail for the cases of the two and three data. (3 figs.)

  19. General activities of JAERI nuclear data center and Japanese nuclear data committee

    International Nuclear Information System (INIS)

    Fukahori, Tokio

    1999-01-01

    The nuclear data center of Japan Atomic Energy Research Institute (JAERI/NDC) is playing the role of Japanese domestic nuclear data center and gateway to foreign data centers. As the domestic nuclear data center, activities of JAERI/NDC are 1) compiling the Japanese Evaluated Nuclear Data Library (JENDL) for both general and special purposes, 2) importing and exporting nuclear data, 3) nuclear data services for the domestic users, and 4) organizing japanese Nuclear Data Committee (JNDC) as a secretariat. Compiled JENDL General Purpose Files up to now are JENDL-1, 2, 3, 3.1 and 3.2. The data for 340 nuclei in the energy range from 10 -5 eV to 20 MeV are available in JENDL-3.2. JENDL Special Purpose Files were also prepared in order to meet the requests from the specified application fields. JNDC has about 140 members. JNDC consists of Main Committee, Steering Committee, Subcommittee on Nuclear Data, Subcommittee on Reactor Constants, Subcommittee on Nuclear Fuel Cycle and Standing Groups. Above subcommittees are performing essential evaluation for the files described above, checking the JENDL files through the benchmark and integral testing as well as considering the standard group constant, and considering about evaluation of decay heat and nuclide generation/depletion and fission product yields. (author)

  20. ZZ-FSXLIB-JD99, MCNP nuclear data library based on JENDL Dosimetry File 99

    International Nuclear Information System (INIS)

    Shibata, Keiichi

    2007-01-01

    Description: JENDL Dosimetry File 99 processed into ACE for Monte Carlo calculations. JENDL/D-99 based MCNP library. Format: ACE. Number of groups: Continuous energy cross section library. Nuclides: 47 Nuclides and 67 reactions: Li-6 (n, triton) alpha; Li-6 alpha-production; Li-7 triton- production; B-10 (n, alpha) Li-7; B-10 alpha-production; F-19 (n, 2n) F-18; Na-23 (n, 2n) Na-22; Na-23 (n, gamma) Na-24; Mg-24 (n, p) Na-24; Al-27 (n, p) Mg-27; Al-27 (n, alpha) Na-24; P-31 (n, p) Si-31; S-32 (n, p) P-32; Sc-45 (n, gamma) Sc-46; Ti-nat (n, x) Sc-46; Ti-nat (n, x) Sc-47; Ti-nat (n, x) Sc-48; Ti-46 (n, 2n) Ti-45; Ti-46 (n, p) Sc-46; Ti-47 (n, np) Sc-46; Ti-47 (n, p) Sc-47; Ti-48 (n, np) Sc-47; Ti-48 (n, p) Sc-48; Ti-49 (n, np) Sc-48; Cr-50 (n, gamma) Cr-51; Cr-52 (n, 2n) Cr-51; Mn-55 (n, 2n) Mn-54; Mn-55 (n, gamma) Mn-56; Fe-54 (n, p) Mn-54; Fe-56 (n, p) Mn-56; Fe-57 (n, np) Mn-56; Fe-58 (n, gamma) Fe-59; Co-59 (n, 2n) Co-58; Co-59 (n, gamma) Co-60; Co-59 (n, alpha) Mn-56; Ni-58 (n, 2n) Ni-57; Ni-58 (n, p) Co-58; Ni-60 (n, p) Co-60; Cu-63 (n, 2n) Cu-62; Cu-63 (n, gamma) Cu-64; Cu-63 (n, alpha) Co-60; Cu-65 (n, 2n) Cu-64; Zn-64 (n, p) Cu-64; Y-89 (n, 2n) Y-88; Zr-90 (n, 2n) Zr-89; Nb-93 (n, n') Nb-93m; Nb-93 (n, 2n) Nb-92m; Rh-103 (n, n') Rh-103m; Ag-109 (n, gamma) Ag-110m; In-115 (n, n') In-115m; In-115 (n, gamma) In-116m; I-127 (n,2n) I-126; Eu-151 (n, gamma) Eu-152; Tm-169 (n,2n) Tm-168; Ta-181 (n, gamma) Ta-182; W-186 (n, gamma) W-187; Au-197 (n, 2n) Au-196; Au-197 (n, gamma) Au-198; Hg-199 (n, n') Hg-199m; Th-232 - fission; Th-232 (n, gamma) Th-233; U-235 - fission; U-238 - fission; U-238 (n, gamma) U-239; Np-237 - fission; Pu-239 - fission; Am-241 - fission. The data were produced on the 31 of March, 2006

  1. Nuclear data requirements for fusion reactor nucleonics

    International Nuclear Information System (INIS)

    Bhat, M.R.; Abdou, M.A.

    1980-01-01

    Nuclear data requirements for fusion reactor nucleonics are reviewed and the present status of data are assessed. The discussion is divided into broad categories dealing with data for Fusion Materials Irradiation Test Facility (FMIT), D-T Fusion Reactors, Alternate Fuel Cycles and the Evaluated Data Files that are available or would be available in the near future

  2. Report to the DOE Nuclear Data Committee, 1991

    International Nuclear Information System (INIS)

    Resler, D.A.; White, R.M.

    1991-03-01

    This document provides a discussion of charged-particle evaluations for applications; advanced modeling of reaction cross sections for light nuclei; thermonuclear data file (TDF) -- a processed file for thermonuclear applications; evaluation of (n,2n) reactions on isotopes of Y and Zr; extension of the LLNL evaluated nuclear database (ENDL) to 30 MeV; and calculated kerma values

  3. Nuclear data online at the NNDC

    International Nuclear Information System (INIS)

    McLane, V.

    1998-03-01

    The National Nuclear Data Center (NNDC) is funded by the US Department of Energy to provide services in the field of low and medium energy nuclear physics to users in the US and Canada. The National Nuclear Data Center (NNDC) Online Data Service, available since 1986, is continually being upgraded and expanded. Most files are now available for access through the WorldWideWeb. Bibliographic, experimental, and evaluated data files are available containing information on neutron, charged-particle, and photon-induced nuclear reaction data, as well as nuclear decay and nuclear structure information. The information available to the users of NNDC services is the product of the combined efforts of the NNDC and cooperating data centers and other interested groups, both in the US and worldwide

  4. Nuclear data newsletter. No. 23

    International Nuclear Information System (INIS)

    1997-04-01

    This issue of the Nuclear Data Newsletter dated April 1997 gives information on the following topics: New nuclear data libraries received including package of eleven data libraries, Chart of nuclides, Conference announcements, Nuclear data handbooks, Selected reports and documents on nuclear data. The addresses of the co-operating nuclear data SERVICE centers are given. The method of accessing to NDIS via Internet (TCP/IP) and to open areas for FTP file transfer are explained

  5. BROND: USSR recommended evaluated neutron data library

    International Nuclear Information System (INIS)

    Manokhin, V.N.

    1988-03-01

    BROND is the recommended evaluated data library of the USSR for neutron induced nuclear reactions. It is a computer library recorded on magnetic tape presented in the internationally recommended format ENDF-5. It contains 65 files with recommended data for 65 elements or isotopes. For each file the present report gives a summary documentation on the contents, the evaluation methods and the originators of the files. (author). Refs

  6. ORACL program file for acquisition, storage and analysis of data in radiation measurement and nondestructive measurement of nuclear material, vol. 2

    International Nuclear Information System (INIS)

    Yagi, Hideyuki; Takeuchi, Norio; Gotoh, Hiroshi

    1976-09-01

    The file contains 79 programs for radiation measurement and nondestructive measurement of nuclear material written in conversational language ORACL associated with the GAMMA-III system of ORTEC Incorporated. It deals with data transfers between disk/core/MCA/magnetic tape, edition of data in disks, calculation of the peak area, calculation of mean and standard deviation, reference to gamma-ray data files, accounting, calendar, etc. It also has a support system for micro-computer development. Usages of the built-in functions of ORACL are presented. (auth.)

  7. Development on hybrid evaluated nuclear data library HENDL1.0/MG/MC

    International Nuclear Information System (INIS)

    Xu Dezheng; Gao Chunjing; Zheng Shanliang; Liu Haibo; Zhu Xiaoxiang; Li Jingjing; Wu Yican

    2004-01-01

    A Hybrid Evaluated Nuclear Data Library (HENDL) named as HENDL1.0 has been developed by Fusion Design Study (FDS) team of Institute of Plasma Physics, Academia Sinica (ASIPP) to take into account the requirements in design and research relevant to fusion, fission and fusion-fission sub-critical hybrid reactor. HENDLI1.0 contains one basic evaluated sub-library naming HENDL1.0/E and to processed working sub-libraries naming HENDL1.0/MG and HENDL1.0/MC, respectively. Through carefully comparing, distinguishing and choosing, HENDL1.0/E integrated basic evaluated neutron data files of 213 nuclides from the several main data libraries for evaluated neutron reaction cross sections including ENDF/B-VI (USA), JEF-2.2 (OECD/NEA, Europe), JENDL-3.2 (Japan), CENDL-2 (China), BROND-2 (Russia) and FENDL-2 (IAEA/NDS, ITER program). Based on this, 175-group neutron and 42-group photon neutron-photon coupled multi-group working library HENDL1.0/MG used for discrete ordinate Sn method transport calculation (such as ANISN code) and a compact ENDF form (ACE), continuous energy structure (pointwise) neutron cross section library HENDL1.0/MC for Monte Carlo method transport simulation (as MCMP code) can be attainable with the current group constants processing system NJOY and transport cross section preparation code TRANSX referring to the Vitamin-J energy group structure. In addition, two special bases i.e. transmutation (burnup) library BURNUP. DAT and response function library RESPONSE.DAT, have been also made for fuel cycle calculation and reactivity analyses of nuclear reactor. The relevant sample testing, benchmark checking and primary confirmation are also carried out to assess the validity of multi-purpose data library HENDL1.0. (authors)

  8. Group cross-section processing method and common nuclear group cross-section library based on JENDL-3 nuclear data file

    International Nuclear Information System (INIS)

    Hasegawa, Akira

    1991-01-01

    A common group cross-section library has been developed in JAERI. This system is called 'JSSTDL-295n-104γ (neutron:295 gamma:104) group constants library system', which is composed of a common 295n-104γ group cross-section library based on JENDL-3 nuclear data file and its utility codes. This system is applicable to fast and fusion reactors. In this paper, firstly outline of group cross-section processing adopted in Prof. GROUCH-G/B system is described in detail which is a common step for all group cross-section library generation. Next available group cross-section libraries developed in Japan based on JENDL-3 are briefly reviewed. Lastly newly developed JSSTDL library system is presented with some special attention to the JENDL-3 data. (author)

  9. Nuclear Reaction Data Centers

    International Nuclear Information System (INIS)

    McLane, V.; Nordborg, C.; Lemmel, H.D.; Manokhin, V.N.

    1988-01-01

    The cooperating Nuclear Reaction Data Centers are involved in the compilation and exchange of nuclear reaction data for incident neutrons, charged particles and photons. Individual centers may also have services in other areas, e.g., evaluated data, nuclear structure and decay data, reactor physics, nuclear safety; some of this information may also be exchanged between interested centers. 20 refs., 1 tab

  10. Update neutron nuclear data evaluation for 236,238Np

    International Nuclear Information System (INIS)

    Chen, Guochang; Wang, Jimin; Yu, Baosheng; Cao, Wentian; Tang, Guo-you

    2015-01-01

    The nuclear data with high accuracy for actinides play an important role in nuclear technology applications, including reactor design and operation, fuel cycle, estimation of the amount of minor actinides (MAs) in high burnup reactors and to research to transmute the MAs to short half-lived nuclides or stable ones. The nuclides of 236 Np are generated via the α-decay of 240 Am or 237 Np(n, 2n) and 237 Np(d, t) reactions. And the nuclides of 238 Np are generated via the α-decay of 242 Am or 237 Np(n, γ) and 237 Np(d, p) reactions. In the present work, according to the systematic trend of the total cross section and elastic cross section etc. of different Np isotopes, and based on the neutron optical model parameters (OMP) of 237 Np, a new set of neutron optical model parameters were obtained for 236,238 Np. Based on the new set OMP and the systematic trend of the cross sections of different Np isotopes, a full set of 236,238 Np neutron nuclear data has been updated and improved by theoretical calculation. The present result has significant improvements over the data in CENDL-3.1

  11. Empire-3.2 Malta. Modular System for Nuclear Reaction Calculations and Nuclear Data Evaluation. User's Manual

    International Nuclear Information System (INIS)

    Herman, M.; Capote, R.; Sin, M.

    2013-08-01

    EMPIRE is a modular system of nuclear reaction codes, comprising various nuclear models, and designed for calculations over a broad range of energies and incident particles. The system can be used for theoretical investigations of nuclear reactions as well as for nuclear data evaluation work. Photons, nucleons, deuterons, tritons, helions ( 3 He), α's, and light or heavy ions can be selected as projectiles. The energy range starts just above the resonance region in the case of a neutron projectile, and extends up to few hundred MeV for heavy ion induced reactions. The code accounts for the major nuclear reaction models, such as optical model, Coupled Channels and DWBA (ECIS06 and OPTMAN), Multi-step Direct (ORION + TRISTAN), NVWY Multi-step Compound, exciton model (PCROSS), hybrid Monte Carlo simulation (DDHMS), and the full featured Hauser-Feshbach model including width fluctuations and the optical model for fission. Heavy ion fusion cross section can be calculated within the simplified coupled channels approach (CCFUS). A comprehensive library of input parameters based on the RIPL-3 library covers nuclear masses, optical model parameters, ground state deformations, discrete levels and decay schemes, level densities, fission barriers, and γ-ray strength functions. Effects of the dynamic deformation of a fast rotating nucleus can be taken into account in the calculations (BARFIT, MOMFIT). The results can be converted into the ENDF-6 format using the accompanying EMPEND code. Modules of the ENDF Utility Codes and the ENDF Pre-Processing codes are applied for ENDF file verification. The package contains the full EXFOR library of experimental data in computational format C4 that are automatically retrieved during the calculations. EMPIRE contains the resonance module that retrieves data from the electronic version of the Atlas of Neutron Resonances by Mughabghab (not provided with the EMPIRE distribution), to produce resonance section and related covariances for the

  12. 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).

  13. NURE [National Uranium Resource Evaluation] HSSR [Hydrogeochemical and Stream Sediment Reconnaissance] Introduction to Data Files, United States: Volume 1

    International Nuclear Information System (INIS)

    1985-01-01

    One product of the Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) program, a component of the National Uranium Resource Evaluation (NURE), is a data-base of interest to scientists and professionals in the academic, business, industrial, and governmental communities. This database contains individual records for water and sediment samples taken during the reconnaissance survey of the entire United States, excluding Hawaii. The purpose of this report is to describe the NURE HSSR data by highlighting its key characteristics and providing user guides to the data. A companion report, ''A Technical History of the NURE HSSR Program,'' summarizes those aspects of the HSSR Program which are likely to be important in helping users understand the database. Each record on the database contains varying information on general field or site characteristics and analytical results for elemental concentrations in the sample; the database is potentially valuable for describing the geochemistry of specified locations and addressing issues or questions in other areas such as water quality, geoexploration, and hydrologic studies. This report is organized in twelve volumes. This first volume presents a brief history of the NURE HSSR program, a description of the data files produced by ISP, a Users' Dictionary for the Analysis File and graphs showing the distribution of elemental concentrations for sediments at the US level. Volumes 2 through 12 are comprised of Data Summary Tables displaying the percentile distribution of the elemental concentrations on the file. Volume 2 contains data for the individual states. Volumes 3 through 12 contain data for the 1 0 x 2 0 quadrangles, organized into eleven regional files; the data for the two regional files for Alaska (North and South) are bound together as Volume 12

  14. Evaluation of nuclear data for emergency preparedness system of nuclear power plants. Comparison of radioactivity inventories by newest nuclear data and rather older nuclear data

    International Nuclear Information System (INIS)

    Yoshida, Yoshitaka; Kimura, Itsuro

    2004-01-01

    The radioactivity inventories for emergency preparedness systems of nuclear power plants calculated by the combination of the generally-used in Japan (general-version), the INSS used by the present authors (INSS-version) and the newest nuclear data library and codes (newest-version) were compared, and the maintaining of conservativeness of the general-version and the INSS-version against the newest-version was examined. And the influences of the radioactivity inventories by the difference between the nuclear cross section and fission yield data, decay data and calculation codes were investigated. As a result, (1) the radioactivity inventories calculated by general-version and INSS-version were not confirmed the conservativeness to the newest-version. But the difference was less than 10%, and it would not give large influence to the calculation of the emergency preparedness system of nuclear plants. (2) The influence of the radioactivity inventories such as 135 Xe build-up were observed by the difference of neutron flux level in an operation of reactors that occurred by the variety of nuclear cross section and fission yield data. (3) Little influence by the variety of decay data was confirmed. (4) The ORIGEN2.1 code underestimated the amount of fission products generated by fission of minor actinides. From these result, the radioactivity inventories for the emergency preparedness system of nuclear power plants are recommended to use the calculation results by the combination of the library for ORIGEN2 based on JENDL3.3 and the ORIGEN2.2 code. (author)

  15. Nuclear data evaluation for 239Pu in the energy region 100 075. ev - 15 MeV

    International Nuclear Information System (INIS)

    Antsipov, G.V.; Bakhanovich, L.A.; Zharkov, V.F.

    1981-06-01

    The present work incorporates the results of the new nuclear data evaluation for 239 Pu. The complete file compiled by the authors in 1974 was practically completely re-examined. The most substantial changes were made above 0.5 keV. In the region of unresolved resonances (0.3-100 keV), the channel contribution to the process widths for a given state and some other aspects were taken into account. The fission cross section and the α-value were evaluated with regard for the correlation of experimental errors. The non-spherical potential with optimized parameters was used to make calculations by the optical and statistical models. The contribution of pre-equilibrium emission was taken into account in calculations of secondary neutron spectra. The new standard anti nusub(sp)( 252 Csub(f)) was used to calculate anti nusub(p). The 26-group constants and g-Westcott factors were obtained from the evaluated data. The complete file of the evaluated data for 239 Pu is presented in the ENDF/B format and conveyed to the Nuclear Data Section of the IAEA. (author)

  16. Evaluation of neutron nuclear data for 7Li

    International Nuclear Information System (INIS)

    Yu Baosheng; Cai Dunjiu

    1993-01-01

    New complete neutron data for 7 Li have been evaluated for CENDL-2. It updates our work in 1978 for CENDL-1 to extend incident neutron energy range from 10 -5 eV to 20 MeV. Combining new experimental data and benchmark testing, the tritium production cross section were improved. The comparison of present evaluation with ENDF/B-6 and JENDL-3 has been made

  17. Compilation and evaluation of fission yield nuclear data

    International Nuclear Information System (INIS)

    Lammer, M.

    1991-09-01

    The task of this meeting was to review the progress made since the previous meeting on fission yield evaluation and to define the tasks for an IAEA Co-ordinated Research Programme in detail. Improvements have been noted in measured data, model calculations and the situation of fission yield evaluation. Tabs

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

    International Nuclear Information System (INIS)

    Goulo, V.; Lorenz, A.

    1988-01-01

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

  19. The role of desk calculators in nuclear data evaluation

    International Nuclear Information System (INIS)

    Motta, M.

    1980-01-01

    The performances of the modern Desk Calculators are more and more increasing. Consequently, the best feature for the definition of a Desk Calculator seems to be prices and volume occupation. The interactive operating mode and the low installation and maintaining costs make the use of these computing machines very likely and economical. A list of tasks which are profitably performed in nuclear data preparation are presented here. A lot of practical applications are given through the formulas and the list of codes written in BASIC language, which is commonly adopted for these small computers. (author)

  20. EXFOR-VIEN. Various international evaluated neutron data in EXFOR format

    International Nuclear Information System (INIS)

    Okamoto, K.; Schwerer, O.; Lemmel, H.D.

    1982-03-01

    The EXFOR-VIEN file contains various evaluated neutron nuclear data that are not part of one of the major evaluated nuclear data libraries. This document summarizes the contents of the EXFOR-VIEN file. The data are available, costfree, from the IAEA Nuclear Data Section on magnetic tape or in printed form. (author)

  1. EXFOR-VIEN. Various international evaluated neutron data in EXFOR format

    International Nuclear Information System (INIS)

    Okamoto, K.; Schwerer, O.; Lemmel, H.D.

    1984-07-01

    The EXFOR-VIEN file contains various evaluated neutron nuclear data that are not part of one of the major evaluated nuclear data libraries. This document summarizes the contents of the EXFOR-VIEN file. The data are available, costfree, from the IAEA Nuclear Data Section on magnetic tape or in printed form. (author)

  2. 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.

  3. Nuclear data newsletter. No. 22

    International Nuclear Information System (INIS)

    1996-11-01

    This issue of the Nuclear Data Newsletter dated November 1996 gives information on the following topics: Online nuclear data service, Fendl summary, Fendl Benchmarks, Information about how access to Fendl files could be done, Information about the IAEA Nuclear Data Section's home page on Internet, New nuclear data libraries received including package of nine data libraries, Chart of nuclides, Nuclear data processing computer codes, Data indexes and bibliographies, Selected reports and documents on nuclear data, Conference proceedings, Nuclear data handbooks. Conference announcements and the addresses of the co-operating nuclear data service centers are included. The method of accessing to NDIS via Internet (TCP/IP) and to open areas for FTP file transfer are explained

  4. 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)

  5. Internet services for nuclear data

    International Nuclear Information System (INIS)

    Chang, Jong hwa

    1998-01-01

    Modern internet technology make it possible to acquire the up to data and reliable nuclear data easily for the user. Main international and national centers distributing the nuclear data are as follows: · IAEA Nuclear Data Section (http://www-nds.iaea.or.at/) · NEA Databank (http://www.nea.fr/html/databank/) · BNL National Nuclear Data Center (http://www.nndc.bnl.gov/) · LANL T2 (http://t2.lanl.gov/) · JAERI Japanese Nuclear Data Center (http://www.nndc.tokai.jaeri.go.jp/) KAERI is also servicing a nuclear data web server since 1994(http://hpngp01.kaeri.re.kr/). The target customers for the KAERI web server are those who are not so familiar with the conventions of nuclear data production society. The server has a 'Table of Nuclides' with graphic interface which contains the mass of nuclides, the decay and half life, the decay scheme, the neutron capture cross section, the fission yields and the neutron cross section. An interactive cross section plotter is provided to compare the cross sections between each evaluated files. We have archived the MCNP library sets, which were processed upon the request from domestic users. An electron and X-ray attenuation factor calculator is also provided for medical scientists

  6. ZZ FENDL-2, Evaluated Nuclear Data Library for Fusion Neutronics Applications

    International Nuclear Information System (INIS)

    2005-01-01

    Description: FENDL: Fusion Evaluated Nuclear Data Library. Materials/nuclides: H 1 , H 2 , H 3 , He 3 , He 4 , Li 6 , Li 7 , Be 9 , B 10 , B 11 , C 12 , N 14 , N 15 , O 16 , F 19 , Na 23 , Mg nat , Al 27 , Si 28 , Si 29 , Si 30 , P 31 , S nat , Cl 35 , Cl 37 , K nat , Ca nat , Ti 46 , Ti 47 , Ti 48 , Ti 49 , Ti 50 , V nat , Cr 50 , Cr 52 , Cr 53 , Cr 54 , Mn 55 , Fe 54 , Fe 56 , Fe 57 , Fe 58 , Co 59 , Ni 58 , Ni 60 , Ni 61 , Ni 62 , Ni 64 , Cu 63 , Cu 65 , Ga nat , Zr nat , Nb 93 , Mo 92 , Mo 94 , Mo 95 , Mo 96 , Mo 97 , Mo 98 , Mo 100 , Sn nat , Ta 181 , W 182 , W 183 , W 184 , W 186 , Au 197 , Pb 206 , Pb 207 , Pb 208 , Bi 209 . Photo-atomic data. IAEA1364/02: FENDL version 2.0 consists of the following sub-libraries: - ACTIVATION (FENDL/A-2.0)- neutron activation cross sections for 13006 reactions on 739 targets ranging from 1-H up to 248-Cm at incident energies up to 20 MeV. Pointwise and processed data in different formats are included. Plots are available. - DECAY (FENDL/D-2.0) - decay properties (decay type, decay energy, and half life) for 1867 nuclides and isomers. FENDL/D-2.0 sub-library is complementary to the activation sub-library. Pointwise and processed data are included. - DOSIMETRY (FENDL/DS-2.0) - neutron cross sections to be used for reactor neutron dosimetry by foil activation, radiation damage cross-sections, and benchmark neutron spectra. This sub-library is identical to the International Reactor Dosimetry File (IRDF-90). Pointwise and processed data are included. - FUSION (FENDL/C-2.0) - charged-particle cross sections for the following fusion reactions: 1-H 2 (d,n)2-He 3 , 1-H 2 (d,p)1-H 3 , 2-He 3 (d,p)2-He 4 , 1-H-3(t,2n)2-He 4 , and 1-H 3 (d,n)2-He 4 . Pointwise and processed data are included. - TRANSPORT - validated basic nuclear data (neutron-nucleus interaction including photon production, and photon-atom interaction cross sections) for 57 nuclides relevant for fusion. In addition to the pointwise data (FENDL/E-2.0), the sub

  7. 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.

  8. Presentations and documents submitted to the 27. meeting of the Working Party on International Nuclear Data Evaluation Co-operation (WPEC), NEA Headquarters, 21-22 May 2015

    International Nuclear Information System (INIS)

    Chadwick, Mark; Danon, Yaron; Dunn, Mike; Herman, Mike; Kahler, Albert; Fischer, Ulrich; Jacqmin, Robert; Koning, Arjan; Plompen, Arjan; Fukahori, Tokio; Harada, Hideo; Igashira, Masayuki; Iwamoto, Osamu; Yokoyama, Kenji; Golashvili, Tengiz; Ignatiev, Victor; Ignatyuk, Anatoly; Oleynik, Dimitry S.; Sinitsa, Valentin; Ge, Zhigang; Trkov, Andrej; De Saint Jean, Cyrille; Kawano, Toshihiko; Schillebeeckx, Peter; Mills, Robert; Mcnabb, Dennis; Palmiotti, Giuseppe; Cabellos, Oscar; ); Lee, Young-Ouk; Kim, Do Heon; Ruan, Xichao; Wu, Haicheng

    2015-05-01

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countries) and CENDL (China) in close co-operation with the Nuclear Data Section of the International Atomic Energy Agency (IAEA). The working party was established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, validation, and related topics, and to provide a framework for co-operative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint evaluation and/or measurement efforts. This document brings together the available documents and presentations relative to this meeting: the agenda, the Summary record of the previous meeting held on May 2014, the Reports (slides) on experimental activities from Europe, Japan, USA, Russia and China, the Brief progress reports from the evaluation projects (ENDF, JEFF, JENDL, ROSFOND, CENDL, IAEA, TENDL), the presentation from Subgroup 39 (Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files) and from Subgroup 41 (Improving nuclear data accuracy of 241 Am and 237 Np capture cross-sections). The document ends with a preliminary proposal for a New Subgroup 42 (Thermal Scattering Kernel S(α,β): Measurement, Evaluation and Application)

  9. Meeting Nuclear Data Needs for Advanced Reactor System. A report by the Working Party on International Evaluation Cooperation of the NEA Nuclear Science Committee

    International Nuclear Information System (INIS)

    Harada, H.; Shibata, K.; Nishio, K.; Plompen, A.; Hambsch, F.J.; Schillebeeckx, P.; ); Igashira, M.; Gunsing, F.; Ledoux, X.; Palmiotti, G.; Haight, R.; Ullmann, J.; Tovesson, F.; Nelson, R.; Herman, M.; Hoblit, S.; Pronyaev, V.; Cano-Ott, D.; Junghans, A.; Calviani, M.; ); Schmidt, K.H.; ); Otsuka, N.; ); Dupont, E.; )

    2013-01-01

    The Working Party on International Nuclear Data Evaluation Co-operation (WPEC) was established under the aegis of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data evaluations, validation and related topics. Its aim is also to provide a framework for co-operative activities between the members of the major nuclear data evaluation projects. This includes the possible exchange of scientists in order to encourage co-operation. Requirements for experimental data resulting from this activity are compiled. The WPEC determines common criteria for evaluated nuclear data files with a view to assessing and improving the quality and completeness of evaluated data. The parties to the project are: ENDF (United States), JEFF/EFF (NEA Data Bank member countries) and JENDL (Japan). Co-operation with evaluation projects of non-OECD countries, specifically the Russian BROND and Chinese CENDL projects, are organized through the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report was issued by WPEC Subgroup 31, whose mission was to utilize the collective knowledge of the international nuclear data measurement community to consider the appropriate resources to address and meet the data needs quantified by WPEC Subgroup 26 for Advanced Reactor Systems. Members of Subgroup 31 performed reviews of uncertainty evaluations by evaluators, of state-of-art experimental techniques, of current experimental situations, and summarized an appropriate path to meet the requirements. To meet the requirement of accurate nuclear data for developing advanced nuclear systems, pertinent efforts of experiments and evaluations are still required and indispensable. As described in Chapter 3, there are striking technical advancements in nuclear data measurement methods. For example, high-intensity-pulsed neutrons generated by spallation reaction at CERN in Europe, LANCE in USA, and J-PARC in Japan become available to obtain high

  10. Progress on chinese evaluated nuclear parameter library: Pt.5

    Energy Technology Data Exchange (ETDEWEB)

    Zongdi, Su; Zhongfu, Huang; Jianfeng, Liu [and others

    1996-06-01

    The progress on chinese evaluated nuclear parameter library (v) was introduced. Six sub-libraries, MCC, DLS, NLD, GDP, FBP and OMP, including their data files and management-retrieval code systems have all been finished. All six sub-libraries have been used in nuclear model calculations, nuclear data evaluations and other fields in China. The applied results show that our evaluated nuclear parameter library is satisfactory and convenient.

  11. CMB v. 1.1 Data Acquisition and Evaluation System of the Cracow Nuclear Microprobe

    International Nuclear Information System (INIS)

    Lekki, J.; Hajduk, R.; Potempa, A.; Pieprzyca, T.; Stachura, Z.; Zieblinski, M.; Styczen, J.; Lebed, S.

    2000-11-01

    An overview of the Cracow nuclear microprobe together with its data acquisition and control system is presented. Magnetic deflection was applied for beam scanning, while detector signals acquisition is performed by the NIM/CAMAC modules under supervision of a Windows operating system running on a PC equipped with the GPIB controller card. Total spectra from every detector are accessible on-line during the measurement, while full information about detected energy and beam position is stored to a disk file in the list mode to allow off-line data analysis. System hardware and software setups together with software operations and data formats used for information storing are described. (author)

  12. Evaluation of Neutron Nuclear Data for Natural Titanium and Antimony

    Institute of Scientific and Technical Information of China (English)

    1989-01-01

    <正> The evaluations of neutron data of natural titanium and antimony are performedin the energy range from 10-5 eV to 20 MeV.The following data are included:resonance parameters,cross sections of total,elastic seattering,nonelastic sea-ttering,inelastic seattering,(n,2n),(n,3n),and(n,X)(X=p,d,t,3He,α)reactions etc.The angular distributions and energy distributions of secondaryneutrons are also given.The reproduced cross sections from resolved and unresolved

  13. IAEA Nuclear Data Section: Progress Report, 2011/12 Summary of Nuclear Data Activity by Staff of the IAEA Nuclear Data Section, May 2011 - April 2012

    International Nuclear Information System (INIS)

    Forrest, R.; Otsuka, N.; Semkova, V.; Simakov, S.P.; Zerkin, V.

    2012-01-01

    Progress report on nuclear data activity by staff of the IAEA Nuclear Data Section from May 2011 - April 2012: 1) Staff changes 2) Data compilations, EXFOR transmission, EXFOR quality control, EXFOR coverage control, Workshops and meetings in 2011/2012 relevant to EXFOR, CINDA, Evaluated data libraries, files and programs 3) Services, software 4) Visits and Inter-centre cooperation (2011-2012) 5) Nuclear data developments 6) Publications.

  14. Communication of nuclear data progress (No.29)

    International Nuclear Information System (INIS)

    2003-01-01

    This is the 29th issue of Communication of Nuclear Data Progress (CNDP), in which the progress and achievements in nuclear data field in 2002 in China are carried. It includes the evaluations of complete neutron data for n+ 55,58 Mn, 99,100 Mo and covariance data evaluation for 63,65,Nat Cu; the evaluations of mass distribution data from 252 Cf spontaneous fission, prompt and delayed neutron yields for 233 U; the studies for level width broaden effect; benchmark testing calculation for 232 Th; establishment of file-6 of n+ 12 C for CENDL-3 et al. (authors)

  15. Activities planning of Nuclear Data Center - 1980

    International Nuclear Information System (INIS)

    Nair, R.P.K.

    1980-01-01

    The main process systems of nuclear data files and the actual nuclear data processing implantation in the Instituto de Estudos Avancados, are presented. The research activities of Nuclear Data Center during 1980 in relation to the implantation of file process systems for multigroup cross sections, and the calculations of integral reactor parameters, are described. (M.C.K.) [pt

  16. Joint evaluated file qualification for thermal neutron reactors

    International Nuclear Information System (INIS)

    Tellier, H.; Van der Gucht, C.; Vanuxeem, J.

    1986-09-01

    The neutron and nuclear data which are needed by reactor physicists to perform core calculations are brought together in the evaluated files. The files are processed to provide multigroup cross sections. The accuracy of the core calculations depends on the initial data, which is sometimes not accurate enough. Therefore the reactor physicists carry out integral experiments. We show, in this paper, how the use of these integral experiments and the application of a tendency research method can improve the accuracy of the neutron data. This technique was applied to the validation of the joint evaluated file. For this purpose, 56 buckling measurements and 42 isotopic analysis of irradiated fuel were used. Small modifications of the initial data are proposed. The final values are compared with recent recommended values or microscopic data. 8 refs

  17. Joint evaluated file qualification for thermal neutron reactors

    International Nuclear Information System (INIS)

    Tellier, H.; van der Gucht, C.; Vanuxeem, J.

    1986-01-01

    The neutron and nuclear data which are needed by reactor physicists to perform core calculations are brought together in the evaluated files. The files are processes to provide multigroup cross sections. The accuracy of the core calculations depends on the initial data, which is sometimes not accurate enough. Therefore the reactor physicists carry out integral experiments. The authors show, in this paper, how the use of these integral experiments and the application of a tendency research method can improve the accuracy of the neutron data. This technique was applied to the validation of the Joint evaluated file. For this purpose, 56 buckling measurements and 42 isotopic analysis of irradiated fuel were used. Small modifications of the initial data are proposed. The final values are compared with recent recommended values or microscopic data

  18. Nuclear models to 200 MeV for high-energy data evaluations. Vol.12

    International Nuclear Information System (INIS)

    Chadwick, M.; Reffo, G.; Dunford, C.L.; Oblozinsky, P.

    1998-01-01

    The work of the Nuclear Energy Agency's Subgroup 12 is described, which represents a collaborative effort to summarize the current status of nuclear reaction modelling codes and prioritize desired future model improvements. Nuclear reaction modelling codes that use appropriate physics in the energy region up to 200 MeV are the focus of this study, particularly those that have proved useful in nuclear data evaluation work. This study is relevant to developing needs in accelerator-driven technology programs, which require accurate nuclear data to high energies for enhanced radiation transport simulations to guide engineering design. (author)

  19. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Doh; Kil, Chung Sub [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    Data testing of ENDF/B-VI.2 was performed and ACE-format continuous point-wise cross section library from ENDF/B-VI.2 for MCNP was validated through CSEWG benchmark and power plant mockup experiments. The calculated k-effective of ORNL-1, -2, -3, -4 and -10 with ENDF/B-VI are low by about 0.5% but those of L-7, -8, -9, -10 and -11 show good agreement with experiments. Overall results for uranium core with ENDF/B-VI is low in critically than with ENDF/B-V. The calculated results with ENDF/B-VI for PNL-6 {approx} 12 of plutonium core and PNL-30 {approx} 35 of mixed oxide core show good agreement with the experiments. The results of critically calculation for fast core benchmark do not show large difference between ENDF/B-VI and -V. But the calculated results of reaction rate ratio with ENDF/B-VI are improved, compared with ENDF/B-V. The calculated power distribution for VENUS PWR mockup core and typical BWR core of GE with both of ENDF/B-VI and -V agree well with measured values. From the above results, newly generated MCNP library from ENDF/B-VI is useful for nuclear and shielding design and analysis. 5 figs, 13 tabs, 11 refs. (Author).

  20. International scope of data evaluation

    International Nuclear Information System (INIS)

    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

  1. Co-ordination of the international network of nuclear structure and decay data evaluators

    International Nuclear Information System (INIS)

    Lorenz, A.

    1986-10-01

    The seventh meeting of the International Network of Nuclear Structure and Decay Data (NSDD) Evaluators concentrated on the organizational aspects of the coordination of the NSDD network and on the presentation and discussion of papers related to the physics of evaluation of NSDD. The report contains short status reports from NSDD Network members, the status of the mass-chain and nuclear structure data, a discussion of evaluation rules and procedures and a short presentation of the next activities

  2. 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.

  3. Coordination of the international network of nuclear structure and decay data evaluators

    International Nuclear Information System (INIS)

    Lorenz, A.

    1984-09-01

    This meeting of the International NSDD (Nuclear Structure and Decay Data) Network dealt with problems related to both the coordination of the NSDD network of centres and groups and to physics questions related to the evaluation of NSDD. The status of the mass-chain and nuclear structure data is reviewed and the planned activities are presented

  4. Co-ordination of the international network of nuclear structure and decay data evaluation

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1991-11-01

    The IAEA Nuclear Data Section convened the ninth meeting of the international nuclear structure and decay data network at Kuwait, 10-14 March 1990. The meeting was attended by 19 scientists from 9 Member States and two international organizations, concerned with the compilation, evaluation, and dissemination of nuclear structure and decay data. The document contains a summary and the proceedings of the meeting, and in annexes, status reports of activities in nuclear structure and decay data from the participating centers. A separate abstract was prepared for one of the scientific lectures related to the topics of the meeting which is reproduced in full length. Refs, figs and tabs

  5. Co-ordination of the international network of nuclear structure and decay data evaluators

    International Nuclear Information System (INIS)

    Schmidt, J.J.

    1988-10-01

    The IAEA Nuclear Data Section convened the eighth meeting of the international nuclear structure and decay data network at Ghent, Belgium, 16-20 May 1988. The meeting was attended by 21 scientists from 12 Member States and three international organizations, concerned with the compilation, evaluation, and dissemination of nuclear structure and decay data. This document contains a summary of the meeting, the proceedings of the meeting and in appendices status reports of activities in nuclear structure and decay data from the participating centers. Refs and tabs

  6. Generalized Nuclear Data: A New Structure (with Supporting Infrastructure) for Handling Nuclear Data

    International Nuclear Information System (INIS)

    Mattoon, C.M.; Beck, B.R.; Patel, N.R.; Summers, N.C.; Hedstrom, G.W.; Brown, D.A.

    2012-01-01

    The Evaluated Nuclear Data File (ENDF) format was designed in the 1960s to accommodate neutron reaction data to support nuclear engineering applications in power, national security and criticality safety. Over the years, the scope of the format has been extended to handle many other kinds of data including charged particle, decay, atomic, photo-nuclear and thermal neutron scattering. Although ENDF has wide acceptance and support for many data types, its limited support for correlated particle emission, limited numeric precision, and general lack of extensibility mean that the nuclear data community cannot take advantage of many emerging opportunities. More generally, the ENDF format provides an unfriendly environment that makes it difficult for new data evaluators and users to create and access nuclear data. The Cross Section Evaluation Working Group (CSEWG) has begun the design of a new Generalized Nuclear Data (or 'GND') structure, meant to replace older formats with a hierarchy that mirrors the underlying physics, and is aligned with modern coding and database practices. In support of this new structure, Lawrence Livermore National Laboratory (LLNL) has updated its nuclear data/reactions management package Fudge to handle GND structured nuclear data. Fudge provides tools for converting both the latest ENDF format (ENDF-6) and the LLNL Evaluated Nuclear Data Library (ENDL) format to and from GND, as well as for visualizing, modifying and processing (i.e., converting evaluated nuclear data into a form more suitable to transport codes) GND structured nuclear data. GND defines the structure needed for storing nuclear data evaluations and the type of data that needs to be stored. But unlike ENDF and ENDL, GND does not define how the data are to be stored in a file. Currently, Fudge writes the structured GND data to a file using the eXtensible Markup Language (XML), as it is ASCII based and can be viewed with any text editor. XML is a meta-language, meaning that it

  7. Generalized Nuclear Data: A New Structure (with Supporting Infrastructure) for Handling Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    Mattoon, C.M. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore CA (United States); Beck, B.R.; Patel, N.R.; Summers, N.C.; Hedstrom, G.W. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore CA (United States); Brown, D.A. [National Nuclear Data Center, Upton NY (United States)

    2012-12-15

    The Evaluated Nuclear Data File (ENDF) format was designed in the 1960s to accommodate neutron reaction data to support nuclear engineering applications in power, national security and criticality safety. Over the years, the scope of the format has been extended to handle many other kinds of data including charged particle, decay, atomic, photo-nuclear and thermal neutron scattering. Although ENDF has wide acceptance and support for many data types, its limited support for correlated particle emission, limited numeric precision, and general lack of extensibility mean that the nuclear data community cannot take advantage of many emerging opportunities. More generally, the ENDF format provides an unfriendly environment that makes it difficult for new data evaluators and users to create and access nuclear data. The Cross Section Evaluation Working Group (CSEWG) has begun the design of a new Generalized Nuclear Data (or 'GND') structure, meant to replace older formats with a hierarchy that mirrors the underlying physics, and is aligned with modern coding and database practices. In support of this new structure, Lawrence Livermore National Laboratory (LLNL) has updated its nuclear data/reactions management package Fudge to handle GND structured nuclear data. Fudge provides tools for converting both the latest ENDF format (ENDF-6) and the LLNL Evaluated Nuclear Data Library (ENDL) format to and from GND, as well as for visualizing, modifying and processing (i.e., converting evaluated nuclear data into a form more suitable to transport codes) GND structured nuclear data. GND defines the structure needed for storing nuclear data evaluations and the type of data that needs to be stored. But unlike ENDF and ENDL, GND does not define how the data are to be stored in a file. Currently, Fudge writes the structured GND data to a file using the eXtensible Markup Language (XML), as it is ASCII based and can be viewed with any text editor. XML is a meta-language, meaning that it

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

    Indian Academy of Sciences (India)

    (b) Compilations coordinated by a classical data centre, computerized visual- izations, large data files information management, evaluations, that include nuclear model based predictions, creating ... and resources with a comprehensive approach to cover as many known ADSS de- signs as possible to meet the nuclear data ...

  9. Recent nuclear data work in China

    International Nuclear Information System (INIS)

    Zhigang, Ge

    2014-01-01

    A brief introduction about China nuclear activities will be introduced in this presentation, which includes the view of nuclear data measurement, evaluation activity system of China and the progress of the nuclear data measurements and evaluations during recent years. As the main output of China Nuclear Data Center, the scheme of the new Chinese Evaluated Nuclear Data Library (CENDL) will also be introduced in this article. The new version of CENDL is general purpose evaluated nuclear data file which consists of the neutron reaction sub-library, the activation sub-library, decay data sub-library and fission yield sub-library. CENDL-3.2 can be used for the nuclear engineering, nuclear medicine and nuclear science etc. fields. The CENDL-3.2 is based on the previous version of CENDL and other special purpose libraries established by CNDC, the updated experimental information and new nuclear data evaluation methodologies. The progress of the evaluation methodologies during recent years in China will be introduced in this presentation. (author)

  10. Recent nuclear data work in China

    International Nuclear Information System (INIS)

    Ge Zhigang

    2015-01-01

    A brief of introduction about China nuclear activities will be introduced in this presentation, which including the view of nuclear data measurement, evaluation activity system of China and the progress of the nuclear data measurements and evaluations during recently years. As the main output of China Nuclear Data Center, The scheme of the new Chinese Evaluated Nuclear Data Library (CENDL) will be introduced also in this article. The new version of CENDL is general purpose evaluated nuclear data file which consists of the neutron reaction sub-library, the activation sub-library, decay data sub-library and fission yield sub-library. CENDL-3.2 can be used for the nuclear engineering, nuclear medicine and nuclear science etc. fields. The CENDL-3.2 is based on the previous version of CENDL and other special purpose libraries established by CNDC, the updated experimental information and new nuclear data evaluation methodologies. The progress of the evaluation methodologies during recently years in China will be introduced in this presentation. (author)

  11. Renewal and maintenance of a nuclear structure data file used for the calculations of dose conversion factors

    International Nuclear Information System (INIS)

    Togawa, Orihiko; Yamaguchi, Yukichi

    1996-02-01

    The ENSDF decay data are used as fundamental data to compute radiation data in the DOSDAC code system, which was developed at JAERI, for the calculation of dose conversion factors. The ENSDF decay data have been periodically revised by reviewing new experimental data in the literature under an international network. The use of this data file enables us to calculate radiation data from information which is the newest and internationally recognized. In spite of this advantage, the decay data file is seldom used in applied fields. This is due to some problems to be solved from a viewpoint of the calculation of radiation data, as well as its complicated structure. This report describes methods for renewal and maintenance of the ENSDF decay data used for the calculation of dose conversion factors. In case that the decay data are used directly, attention should be sometimes paid to some problems, for example defects in data. In renewing and using the ENSDF decay data, the DOSDAC code system tries to avoid wrong calculations of radiation data by check and modification of defects in data through four supporting computer codes. (author)

  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. Argonne Nuclear Data Program

    Energy Technology Data Exchange (ETDEWEB)

    Kondev, F. [US Nuclear Data Program, U.S. DOE/SC (United States)

    2013-08-15

    Nuclear Data Compilations and Evaluations: - Nuclear structure and decay data compilations and evaluations for the International NSDD network (ENSDF and XUNDL); - AME12 and NuBase12 - in collaboration with G. Audi and M. MacCormick, CSNSM (Orsay), M. Wang, IMP (Lanzhou) and B. Pfeiffer, GSI (Darmstadt) - presentation by M. Wang; - DDEP coordinator - completed; - Horizontal nuclear data evaluation activities -IAEA CRP's, Isomers, Medical Isotopes; Complementary ND research Activities: - CARIBU, FRIB and other RIB facilities, Gretina, IAEA-CRP - emphasis on nuclear structure physics and astrophysics, and their intersection with applied nuclear physics programs.

  14. Integrated system for production of neutronics and photonics calculational constants. Volume 15, Part C. The LLL Evaluated Nuclear Data Library (ENDL): translation of ENDL neutron-induced interaction data into the ENDF/B format

    International Nuclear Information System (INIS)

    Howerton, R.J.

    1976-01-01

    The LLL evaluated nuclear data library (ENDL) has been translated into the evaluated neutron data file/version B (ENDF/B) format. This translation is for the convenience of those who wish to use ENDL data but who are more familiar with ENDF/B formats and procedures. Only that portion of ENDL dealing with neutron-induced interactions (including photon production from neutron-induced reactions) has been translated

  15. Nuclear data newsletter. No.25

    International Nuclear Information System (INIS)

    1998-06-01

    The issue of the Nuclear Data Newsletter dated June 1998 gives information on the following topics: Computer code development, New data files and libraries, Major outcome of the NDS data development activity, Selected reports and documents on nuclear data, Chart of nuclides, Conference proceedings, Conference and meetings announcement, Forthcoming meetings held by NDS, Technical co-operation programme for 2001-2002, The address of the co-operating nuclear data service centres

  16. Nuclear Data Processing for Reactor Physics Calculation

    International Nuclear Information System (INIS)

    Suwoto; Zuhair; Pandiangan, Tumpal

    2003-01-01

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

  17. Nuclear Structure Data for the Present Age

    International Nuclear Information System (INIS)

    Baglin, Coral M.

    2005-01-01

    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

  18. Compilation and evaluation of fission yield nuclear data. Final report of a co-ordinated research project 1991-1996

    International Nuclear Information System (INIS)

    2000-12-01

    Fission product yields are required at several stages of the nuclear fuel cycle and are therefore included in all large international data files for reactor calculations and related applications. Such files are maintained and disseminated by the Nuclear Data Section of the IAEA as a member of an international data centres network. Users of these data are from the fields of reactor design and operation, waste management and nuclear materials safeguards, all of which are essential parts of the IAEA programme. In the 1980s, the number of measured fission yields increased so drastically that the manpower available for evaluating them to meet specific user needs was insufficient. To cope with this task, it was concluded in several meetings on fission product nuclear data, some of them convened by the IAEA, that international co-operation was required, and an IAEA co-ordinated research project (CRP) was recommended. This recommendation was endorsed by the International Nuclear Data Committee, an advisory body for the nuclear data programme of the IAEA. As a consequence, the CRP on the Compilation and Evaluation of Fission Yield Nuclear Data was initiated in 1991, after its scope, objectives and tasks had been defined by a preparatory meeting. The different tasks, such as special evaluations and development of improved methods, were distributed among participants. The results of the research work were discussed and approved by all participants in research co-ordination meetings. For a successful development of theoretical and empirical models, experiments had to be recommended and their results to be awaited, which made necessary an extension of the CRP by two years. This TECDOC is the result of a joint effort of all participants in this CRP. The individual sections represent CRP tasks and were prepared by the participants responsible for doing the research, some of which comprise significant new scientific developments. The appendices to this book contain voluminous

  19. Transactinium isotope nuclear data - 1984

    International Nuclear Information System (INIS)

    Lorenz, A.

    1984-11-01

    Transactinium isotopes (Z>89) are important in the nuclear fuel cycle of both thermal and fast reactors, and have found increasing areas of applications in science and industry. The document contains the reports of the three working groups of the meeting, on the following: The status of experimental data; The status of evaluated data files; The status and needs for nuclear decay data of Transactinium nuclei. In all three reports both general and specific recommendations are given. Most important achievements, most pressing needs and the remaining data discrepancies are reviewed. The status of the knowledge of the decay data is presented in a table. A list of the review papers presented and of the contributed papers is also given

  20. Working Party on International Nuclear Data Evaluation Co-operation (WPEC). Presentations and documents submitted to the 27. meeting, NEA Headquarters, 21-22 May 2015

    International Nuclear Information System (INIS)

    2015-05-01

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countries) and CENDL (China) in close co-operation with the Nuclear Data Section of the International Atomic Energy Agency (IAEA). The working party was established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, validation, and related topics, and to provide a framework for co-operative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint evaluation and/or measurement efforts. The 27. Meeting of the WPEC was the occasion to review the experimental activities, the evaluation projects and the Status of subgroups. This document brings together the available documents of the meeting: 1 - The Proposed agenda, the list of participants and the Summary record of the previous meeting, May 2014 (Report NEA-SEN-NSC-WPEC--2014-2); 2 - The Reports on experimental activities: Europe (NEA DB), Japan, USA, Russia, China; 3 - Some Brief progress reports from the evaluation projects: ENDF, JEFF, JENDL, BROND/ROSFOND, CENDL, IAEA, and TENDL; 4 - The Status of some subgroups: Subgroup 35 (Scattering angular distribution in the fast energy range); Subgroup 36 (Reporting and usage of experimental data for evaluation in the resolved resonance region); Subgroup 37 (Improved fission product yield evaluation methodologies); Subgroup 38 (A modern nuclear database structure beyond the ENDF format); Subgroup 39 (Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files); Subgroup 40 (Collaborative International Evaluated Library Organisation (CIELO) Pilot Project); Subgroup 41 (Improving nuclear data accuracy of 241 Am and 237 Np capture cross-sections); Subgroup C (High

  1. NNDC [National Nuclear Data Center] support for fusion nuclear data needs

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1988-01-01

    The National Data Center (NNDC) located at Brookhaven National Laboratory is an outgrowth of the Sigma Center founded by D.J. Hughes to compile low energy neutron reaction data in the 1950's. The center has played a lead role in the production of evaluated nuclear data (ENDF/B) for the United States nuclear power program. This data file, now in its sixth version, is produced as a cooperative effort of many DOE funded organizations via the Cross Section Evaluation Working Group (GSEWG). The NNDC's role, in addition to providing the structure and leadership for CSEWG, is to supply compiled bibliographic and experimental data and provide file processing, checking, distribution and documentation services. In the past, the NNDC has also produced nuclear data evaluations.lt. slash

  2. 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.

  3. Sixth research coordination meeting on the measurement and evaluation of transactinium isotope nuclear data

    International Nuclear Information System (INIS)

    Lorenz, A.

    1983-11-01

    Proceedings of the sixth meeting of the participants in the IAEA Coordinated Research Programme to measure and evaluate the required nuclear decay data of heavy element radionuclides, convened by the IAEA Nuclear Data Section on 21-24 June 1983 at Idaho Falls, USA. The meeting participants reviewed the data requirements, updated and extended the recommended list of half-lives, and continued to review the status of alpha and gamma radiation spectra emitted in the decay of transactinium isotopes

  4. JNDC FP decay data file

    International Nuclear Information System (INIS)

    Yamamoto, Tohru; Akiyama, Masatsugu

    1981-02-01

    The decay data file for fission product nuclides (FP DECAY DATA FILE) has been prepared for summation calculation of the decay heat of fission products. The average energies released in β- and γ-transitions have been calculated with computer code PROFP. The calculated results and necessary information have been arranged in tabular form together with the estimated results for 470 nuclides of which decay data are not available experimentally. (author)

  5. Can Experimental Scientists, Data Evaluators and Compilers, and Nuclear Data Users Understand One Another?

    International Nuclear Information System (INIS)

    Usachev, L.N.

    1966-01-01

    The International Atomic Energy Agency organizes conferences on a wide variety of scientific subjects, all of which are of fundamental importance for the development of nuclear power. These include the technology of fuel elements, their stability in neutron fields, and chemical reprocessing as well as reactor physics, mathematical computational methods and the problems of protection and dosimetry. The problem of microscopic nuclear data, an essential aspect of reactor work, is just one of these many subjects. On the other hand, it should be remembered that the possibility of releasing nuclear energy was established in the first place by obtaining nuclear data on the fission process occurring in the uranium nucleus following the capture of a neutron and on the escape of the 2-3 secondary fission neutrons. In early nuclear power work the information provided by nuclear data was of considerable, even of decisive, importance. For example, the information available on the neutron balance in fast reactors showed that such reactors could operate as breeders and thus that it was worth while developing them. Strictly speaking, it is of course difficult to speak of a knowledge of nuclear data at this early period. It is perhaps more accurate to speak of the understanding of and the feeling for such data which grew up on the basis of the existing physical ideas on the fission of the nucleus, radiative capture and neutron scattering. Experimental data were very scanty but for that reason they were particularly valuable

  6. Can Experimental Scientists, Data Evaluators and Compilers, and Nuclear Data Users Understand One Another?

    Energy Technology Data Exchange (ETDEWEB)

    Usachev, L. N. [Institute of Physics and Energetics, Obninsk, USSR (Russian Federation)

    1966-07-01

    The International Atomic Energy Agency organizes conferences on a wide variety of scientific subjects, all of which are of fundamental importance for the development of nuclear power. These include the technology of fuel elements, their stability in neutron fields, and chemical reprocessing as well as reactor physics, mathematical computational methods and the problems of protection and dosimetry. The problem of microscopic nuclear data, an essential aspect of reactor work, is just one of these many subjects. On the other hand, it should be remembered that the possibility of releasing nuclear energy was established in the first place by obtaining nuclear data on the fission process occurring in the uranium nucleus following the capture of a neutron and on the escape of the 2-3 secondary fission neutrons. In early nuclear power work the information provided by nuclear data was of considerable, even of decisive, importance. For example, the information available on the neutron balance in fast reactors showed that such reactors could operate as breeders and thus that it was worth while developing them. Strictly speaking, it is of course difficult to speak of a knowledge of nuclear data at this early period. It is perhaps more accurate to speak of the understanding of and the feeling for such data which grew up on the basis of the existing physical ideas on the fission of the nucleus, radiative capture and neutron scattering. Experimental data were very scanty but for that reason they were particularly valuable.

  7. 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)

    Pronyaev, V G; Nichols, A L; Tuli, J [eds.

    2004-03-01

    The IAEA Nuclear Data Section convened the 15th meeting of the Network of Nuclear Structure and Decay Data Evaluators at the IAEA Headquarters, Vienna, 10-14 November 2003. This meeting was attended by 23 scientists from 11 Member States concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, the recommendations, data centre reports and the various proposals considered, modified and agreed by the participants are contained within this document. Nuclear data are essential to the development, implementation and maintenance of all nuclear technologies. The international network of Nuclear Structure and Decay Data (NSDD) Evaluators is sponsored by the IAEA, and consists of evaluation groups and data service centers 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. The results represent the recommended 'best values' for the various nuclear structure and decay data parameters. Recommended values are made available to users by means of various media, such as the world wide web, CD-ROMs, wall charts of the nuclides, handbooks, nuclear wallet cards and others. Participants discussed a wide range of technical matters, and the recommendations of improving the quality of NSDD evaluations. A list of actions was also prepared for implementation during the course of the next two years. NSDD members prepared many recommendations for the IAEA and the major evaluation centers, which are aimed at improving the technical support towards the network and streamlining the organization of work. These consensus conclusions include: the development and exchange of programming products; revision of

  8. Calculation of the neutron activation parameters from recently evaluated nuclear data

    International Nuclear Information System (INIS)

    Lopez Aldama, Daniel; Diaz Martinez, Nereida C.

    1999-01-01

    Neutron Activation Analysis (NAA) requires the values for nuclear data such as the 2200 m/s cross section so, the resonance integral I0, the parameter Q0 and the well-known Westcott factors. The availability of recently evaluated nuclear data libraries as the ENDF/B-VI Rev. 5, JEF 2.2, CENDL-2.1 and JENDL-3.2, makes possible to derive the above quantities from the basic nuclear data. It could be very helpful for those NAA parameters, which are unknown or difficult to measure accurately. The procedure to compute the NAA parameters includes the processing of the evaluated nuclear data and the calculation of each parameter directly from its definition. The evaluated nuclear data libraries ENDF/B-VI Rev. 5 and JENDL 3.2 were selected as the main sources of basic nuclear data. The ENDF pre-processing codes were used for processing the source evaluated data and a modified version of the INTER code was applied to calculate the required NAA integrals. The NAA parameters were computed for more than 30 important isotopes. The obtained results were compared with experimental values whenever possible

  9. The AEP Barnbook DATLIB. Nuclear Reaction Cross Sections and Reactivity Parameter Library and Files

    International Nuclear Information System (INIS)

    Feldbacher, R.

    1987-10-01

    Nuclear reaction data for light isotope charged particle reactions (Z<6) have been compiled. This hardcopy contains file headers, plots and an extended bibliography. Numerical data files and processing routines are available on tape at IAEA-NDS. (author). Refs

  10. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Gil, Choong Sub; Lee, Jong Tai; Hwang, Won Guk [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

    1990-12-01

    A one-group cross section data base used by the ORIGEN2 computer code to simulate the depletion, buildup and decay of radionuclides in research reactor was developed. For this, ENDF/B-IV or -V data was processed using the NJOY code system into 69-group data. The burn-up-dependent weighting spectra were calculated with the WIMS-KAERI code, and then the 69-group data were collapsed to one-group using the spectra. The ORIGEN2 depletion calculations for the KMRR fuel were performed using an old PWR and the new data base. By comparing these results to the WIMS-KAERI calculations, it is seen that the results of actinide composition calculated by the ORIGEN2 with the new data base turn out to be in an excellent agreement with the WIMS-KAERI results in the range up to 120 GWD/MTIHM burnup. (Author).

  11. The program of group constants creation (SMOK) on basis libraries of evaluated nuclear data in ENDE/B format for physical module FORTUN-88

    International Nuclear Information System (INIS)

    Borisov, A.A.

    1991-01-01

    The SMOK program for creation of group microconstants in the FORTUN-88 physical module format providing for calculations of neutron transport by the Monte Carlo method is described. The program processes files of evaluated neutron nuclear data in the ENDF-4 format. The constant structure gives an apportunity to simulate the process of neutron collisions with matter in details. The program service capabilities provide for graphical constant comparison. 11 refs

  12. Role and use of nuclear theories and models in practical evaluation of neutron nuclear data needed for fission and fusion reactor design and other nuclear applications

    International Nuclear Information System (INIS)

    Prince, A.

    1975-01-01

    A review of the various nuclear models used in the evaluation of neutron nuclear data for fission and fusion reactors is presented. Computer codes embodying the principles of the relevant nuclear models are compared with each other and with experimental data. The regions of validity and limitations of the conceptual formalisms are also included, along with the effects of the numerical procedures used in the codes themselves. Conclusions and recommendations for future demands are outlined.15 tables, 15 figures, 90 references

  13. The role and use of nuclear theories and models in practical evaluation of neutron nuclear data needed for fission and fusion reactor design and other nuclear applications

    International Nuclear Information System (INIS)

    Prince, A.

    1976-01-01

    A review of the various nuclear models used in the evaluation of neutron nuclear data for fission and fusion reactors is presented. Computer codes embodying the principles of the relevant nuclear models are compared with each other and with experimental data. The regions of validity and limitations of the conceptual formalisms are also included, along with the effects of the numerical procedures used in the codes themselves. Conclusions and recommendations for future demands are outlined. (author)

  14. Development of web-based user interface for evaluated covariance data files

    International Nuclear Information System (INIS)

    Togashi, Tomoaki; Kato, Kiyoshi; Suzuki, Ryusuke; Otuka, Naohiko

    2010-01-01

    We develop a web-based interface which visualizes cross sections with their covariance compiled in the ENDF format in order to support evaluated covariance data users who do not have experience of NJOY calculation. A package of programs has been constructed without aid of any existing program libraries. (author)

  15. Overview of nuclear data

    International Nuclear Information System (INIS)

    Firestone, R.B.

    2003-01-01

    For many years, nuclear structure and decay data have been compiled and disseminated by an International Network of Nuclear Structure and Decay Data (NSDD) evaluators under the auspices of the International Nuclear Data Committee (INDC) of the International Atomic Energy Agency (IAEA). In this lecture I will discuss the kinds of data that are available and describe various ways to obtain this information. We will learn about some of the publications that are available and Internet sources of nuclear data. You will be introduced to Isotope Explorer software for retrieving and displaying nuclear structure and radioactive decay data. The on-line resources Table of Radioactive Isotopes, PGAA Database Viewer, Nuclear Science Reference Search, Table of Isotopes Educational Website, and other information sources will be discussed. Exercises will be provided to increase your ability to understand, access, and use nuclear data

  16. Generation of multigroup cross sections from ENDF/B-IV nuclear data library

    International Nuclear Information System (INIS)

    Chapot, J.L.C.; Thome Filho, Z.D.

    1980-04-01

    The generation of nuclear data compacted in energy groups is made. The nuclear data library ENDF/B-IV, Evaluated Nuclear Data File, and the new version of the codes ETOG-3 and ETOT-3 are utilized. The data obtained are compared with data from other sources. (L.F.) [pt

  17. INDL/V. IAEA Nuclear Data Library for various neutron data evaluations in ENDF/B-5 format

    International Nuclear Information System (INIS)

    Pronyaev, V.; Cullen, D.; Lemmel, H.D.; McLaughlin, K.; Schwerer, O.

    1982-05-01

    INDL/V is a computerized library for evaluated neutron reaction data of varying origin compiled in ENDF/B-5 format. The data are available costfree on magnetic tape from the IAEA Nuclear Data Section. This document summarizes the contents of the library, including graphical plots of all cross-section data. (author)

  18. 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.

  19. Activities on collection, evaluation and dissemination of non-neutron nuclear data in the USSR

    International Nuclear Information System (INIS)

    Grigor'yan, Yu.I.; Ignatochkin, A.E.; Sokolovskij, L.L.; Chukreev, F.E.

    1976-01-01

    The article describes the present status of collection, evaluation and dissemination of non-neutron nuclear data by the Centre for Data on the Structure of the Atomic Nucleus and Nuclear Reactions, USSR State Committee on the utilization of Atomic Energy. The structure of the Centre itself, its computer facilities and its co-operation with outside organizations are indicated and its functions and plans of activity are considered. (author)

  20. 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).

  1. 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)

  2. Transport code and nuclear data in intermediate energy region

    International Nuclear Information System (INIS)

    Hasegawa, Akira; Odama, Naomitsu; Maekawa, F.; Ueki, K.; Kosaka, K.; Oyama, Y.

    1998-01-01

    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)

  3. Nuclear data project in Korea and resonance parameter evaluation of fission products

    International Nuclear Information System (INIS)

    Chang, Jonghwa; Oh, Soo-Youl

    2000-01-01

    Nuclear data activities in the fields of evaluation, processing, measurement, and service in Korea are presented in this paper. As one of the current activities, the neutron resonance parameters for stable or long-lived nineteen fission products have been evaluated and the results are presented here. (author)

  4. Nuclear Data Newsletter, No. 55, May 2013

    International Nuclear Information System (INIS)

    2013-05-01

    In previous newsletters we have focussed on some aspects of the Section's work such as EXFOR or Atomic and Molecular data. In the current one there are details of the work of the Nuclear Data Development Unit. A major event in the last six months has been the Nuclear Data for Science and Technology ND2013 Conference held in New York, USA. High attendance and high quality of papers indicate the continuing interest in nuclear data worldwide. An area of current discussion is new representations of the familiar data formats established for all data files, evaluated reaction data, experimental reaction data and evaluated structure data. One possibility is the use of XML and this is being discussed in various international fora. Feedback from readers on this topic is very much welcomed

  5. INDL/V (85). IAEA Nuclear Data Library for various neutron data evaluations in ENDF-5 format

    International Nuclear Information System (INIS)

    Lemmel, H.D.; Goulo, V.; McLaughlin, K.; Pronyaev, V.; Schwerer, O.

    1985-06-01

    INDL/V is a computerized library for evaluated neutron reaction data from varying origin compiled in ENDF-5 format. The data are available costfree on magnetic tape from the IAEA Nuclear Data Section. This document summarizes the contents of the library in its version of March 1985. (author)

  6. 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.

  7. Alternate ways for automation of evaluating nuclear physical data reliability from primary literature

    International Nuclear Information System (INIS)

    Golashvili, T.V.; Tsvetaev, S.M.

    1983-01-01

    Methods, possible ways, criteria and algorithms for organizing an automated system for evaluating nuclear physical data reliability from primary literature are discussed. It is noted that automation of data reliability evaluation does not substitute for a scientist dealing with data evaluation. It only releases him from hard, monotonous and tedious work not requiring erudition or profound knowledge. Computers will facilitate and accelerate the work of the expert and, hence, leat to a sharp increase of a bulk of works on evaluation of data reliability

  8. Evaluation of nuclear data for radiation shielding by model calculations and international co-operation aspects

    International Nuclear Information System (INIS)

    Canetta, E.; Maino, G.; Menapace, E.

    2001-01-01

    The matter is reviewed, also following previous discussions at ICRS-9, concerning evaluation and related theoretical activities on nuclear data for radiation shielding within the framework of international co-operation initiatives, according to recognised needs and priorities. Both cross-section data.- for reactions induced by neutrons and photons - and nuclear structure data have been considered. In this context, main contributions and typical results are presented from theoretical and evaluation activities at the ENEA Applied Physics Division, especially concerning neutron induced reaction data up to 20 MeV and photonuclear reaction data such as photon absorption and (gamma,n) cross-sections. Relevant aspects of algebraic nuclear models and of evaporation and pre-equilibrium models are discussed. (authors)

  9. Direct utilization of information from nuclear data files in Monte Carlo simulation of neutron and photon transport

    International Nuclear Information System (INIS)

    Androseno, P.; Zholudov, D.; Kompaniyets, A.; Smirnova, O.

    2000-01-01

    In order to improve both the economics of Nuclear Power Plants (NPPs) as well as their safety, data and computer codes that perform benchmark calculations while simulating NPP parameters must be utilized. This work is mainly concerned with application of computer codes using the Monte Carlo method, which provides advanced accuracy of equations to be calculated. (authors)

  10. ENSDF: a nuclear structure data bank for nuclear physicists

    International Nuclear Information System (INIS)

    Blachot, J.

    1987-02-01

    Data Banks have tremendously grown these last years. All the nuclear Structure information are now in the ENSDF. This file is used for the Nuclear Data Sheets publication. The part which contains only Adopted Data could be used as a Data Bank for Nuclear Physicists. Examples of retrevial are given [fr

  11. Principles and techniques of data evaluation

    International Nuclear Information System (INIS)

    Froehner, F.H.

    1986-08-01

    The probabilistic foundations of data evaluations are reviewed, with special emphasis on parameter estimation based on Bayes' theorem and modern methods concerning prior probabilities. The process leading from raw data to evaluated data files is briefly explained for the example of nuclear reaction cross sections, with a discussion of systematic and statistical errors and their propagation. It is shown how evaluators can establish data covariances if error components are properly specified by experimentalists, and how correlated data uncertainties in covariance files are utilised in sensitivity studies and accuracy assessments. The problem of inconsistent data is also addressed briefly. (orig.) [de

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

    International Nuclear Information System (INIS)

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

    1983-01-01

    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. High energy nuclear data evaluations for neutron-, proton-, and photon-induced reactions at KAERI

    International Nuclear Information System (INIS)

    Lee, Young Ouk; Chang, Jong Hwa; Kim, Doo Hwan; Lee, Jeong Yeon; Han, Yinlu; Sukhovitski, Efrem Sh.

    2001-01-01

    The Korea Atomic Energy Research Institute (KAERI) is building high energy neutron-, proton-, and photon-induced nuclear data libraries for energies up to hundreds MeV in response to nuclear data needs from various R and Ds and applications. The librares provide nuclear data needed for the accelerator-driven transmutation of nuclear waste and radiation transport simulations of cancer radiotherapy. The neutron library currently has 10 isotopes such as C-12, N-14, O-16, Al-27, Si-28, Ca-40, Fe-56, Ni-58, Zr-90, Sn-120, and Pb-208 for energies from 20 up to 400 MeV. The proton nuclear data were evaluated in a consistent manner with the neutron case, using the same nuclear model parameters. In addition to the same isotopes included in the neutron library, the proton library has 70 extra isotopes of 24 elements ranging from nitrogen to lead up to 150 MeV for which the evaluations are focused on the medical and activation analyses applications. The photonuclear data library has been built along with international collaboration by participating in the IAEA's Coordinated Research Project (CRP) which ended last year. Currently the KAERI photonuclear library includes 143 isotopes of 39 elements

  14. 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.

  15. GTNDSE: The GA Tech nuclear data search engine

    International Nuclear Information System (INIS)

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

    2004-01-01

    The function of the search engine is to retrieve data from ENSDF-formatted files and to write data in user-selected format. The purposes are horizontal systematics of nuclear mass surface, comparison with experimental data and to assist in data analysis and evaluation

  16. 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.

  17. Evaluation and benchmarking of nuclear data of vanadium in integral experiments with 14-MeV neutrons

    CERN Document Server

    Blokhin, A I; Chuvilin, D; Livke, A V; Manokhin, V N; Markovskij, D; Nagorny, V; Nefedov, Yu A; Orlov, R; Savin, M; Semenov, V; Shmarov, A; Shvetsov, A M; Zagryadsky, V; Zhitnik, A

    2001-01-01

    The measurements of the gamma-ray and neutron leakage spectra from three vanadium spheres with diameter 10, 24 and 34 cm at their internal irradiation by 14-MeV neutrons were carried out in frame of the ISTC Project no. 910 in collaboration with FZK. All the spheres have the same geometry of the central hole of 3 cm in diameter. The neutron leakage spectra were measured by a scintillation detector, and by a gas proportional counter. The gamma-ray leakage spectra were measured with help of a crystal NaI(Tl). Analysis of these experiments is performed with the new evaluated nuclear data files prepared in frame of the project activities. A comparison of experimental and calculated neutron and gamma-ray leakage spectra from three vanadium spheres is given.

  18. Activity report of Japanese Nuclear Data Committee in period of April 1997 to March 1999

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents the activities of the Japanese Nuclear Data Committee (JNDC) in the period of April 1997 to March 1999. In this period, preparation of the next version of the Japanese Evaluated Nuclear Data Library, JENDL-3.3, has progressed. Generation of the special purpose files also has been advanced. In this report, the activities of each group affiliated by the committee are presented and the following are described as special topics : (1) progress in evaluating JENDL-3.3, (2) production of JENDL Covariance File and its processing system, (3) completion of the JENDL Dosimetry File, and (4) the JENDL FP Decay Data File. (author)

  19. 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.

  20. UK chemical nuclear data committee progress report: data studies during 1989

    International Nuclear Information System (INIS)

    Nichols, A.L.

    1990-01-01

    Basic nuclear data requirements for industrial application are monitored by the UK Chemical Nuclear Data Committee (UKCNDC), covering half-lives, decay data, fission yields and the content of computerised data files. While the UKCNDC Request List was reviewed at the end of 1989 to reveal new and continued requirements, funding problems have increased during the year. Difficulties in the UK nuclear power industry are reflected in the decline in experimental studies, although evaluation efforts have been maintained. (author)

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

    International Nuclear Information System (INIS)

    Fischer, U.; Avrigeanu, M.; Avrigeanu, V.; Cabellos, O.; Kodeli, I.; Koning, A.; Konobeyev, A.Yu.; Leeb, H.; Rochman, D.; Pereslavtsev, P.; Sauvan, P.; Sublet, J.-C.; Trkov, A.; Dupont, E.; Leichtle, D.; Izquierdo, J.

    2014-01-01

    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

  2. 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.

  3. An internet-based teaching file on clinical nuclear medicine

    International Nuclear Information System (INIS)

    Jiang Zhong; Wu Jinchang

    2001-01-01

    Objective: The goal of this project was to develop an internet-based interactive digital teaching file on nuclide imaging in clinical nuclear medicine, with the capability of access to internet. Methods: On the basis of academic teaching contents in nuclear medicine textbook for undergraduates who major in nuclear medicine, Frontpage 2000, HTML language, and JavaScript language in some parts of the contents, were utilized in the internet-based teaching file developed in this study. Results: A practical and comprehensive teaching file was accomplished and may get access with acceptable speed to internet. Besides basic teaching contents of nuclide imagings, a large number of typical and rare clinical cases, questionnaire with answers and update data in the field of nuclear medicine were included in the file. Conclusion: This teaching file meets its goal of providing an easy-to-use and internet-based digital teaching file, characteristically with the contents instant and enriched, and with the modes diversified and colorful

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

    International Nuclear Information System (INIS)

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

    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

  5. The Fusion Evaluated Nuclear Data Library (FENDL). Summary Report of an IAEA Consultants’ Meeting

    International Nuclear Information System (INIS)

    Fleming, Michael; Trkov, Andrej

    2016-08-01

    The Consultants’ Meeting on the Fusion Evaluated Nuclear Data Library (FENDL) was held at the IAEA Headquarters in Vienna from 1 to 4 August 2016. A summary of the presentations, discussions, actions and strategies for the future library versions and distributions are provided in this report. (author)

  6. Nuclear data newsletter. No. 33

    International Nuclear Information System (INIS)

    2002-03-01

    This issue announces the online and offline news concerning a workshop on nuclear structure and decay data evaluation, INDC reports, updated databases and libraries on CD-ROM. In includes announcements on development activities of IAEA in the field of nuclear data collections and relevant computer codes and lists selected reports and documents on nuclear data as well as cooperating nuclear data service centres

  7. Nuclear data newsletter. No. 11

    International Nuclear Information System (INIS)

    1987-10-01

    This issue announces nuclear data libraries received by the IAEA Nuclear Data Section: ENDF/B-6 standards; Cf-252 neutron spectrum; Chinese Evaluated Fission-Product Yield Library; DRSG-87; RSIC Photon Interaction Library; DAMSIG84; nuclear data processing codes; and nuclear data handbooks. A list of a selection of new relevant documents is included

  8. WRENDA 83/84. World request list for nuclear data

    International Nuclear Information System (INIS)

    Piksaikin, V.

    1983-11-01

    WRENDA 83/84 is the eighth edition of the World Request List for Nuclear Data. This list is produced from a computer file of nuclear data requests, maintained by the Nuclear Data Section of the International Atomic Energy Agency (IAEA). The requests are provided by official bodies, such as national nuclear data committees, through four regional data centers serving all Member States of the IAEA. Each request included indicates: that the estimated accuracy of the nuclear data available does not satisfy the requirements encountered, and that, consequently, new data measurements and/or data evaluations with improved accuracy are highly desirable. WRENDA is intended to serve as a guide to experimentalists, evaluators and administrators when planning nuclear data measurement and evaluation programs. The requests in this edition come from 15 different countries and one international organization. (author)

  9. Workshop on nuclear structure and decay data: Theory and evaluation manual - Pt. 2

    International Nuclear Information System (INIS)

    Nichols, A.L.; McLaughlin, P.K.; p.mclaughlin@iaea.org

    2004-11-01

    A two-week Workshop on Nuclear Structure and Decay Data: Theory and Evaluation was organized and administrated by the IAEA Nuclear Data Section, and hosted at the Abdus Salam International Centre for Theoretical Physics (ICTP) in Trieste, Italy from 17 to 28 November 2003. The aims and contents of this workshop are summarized, along with the agenda, list of participants, comments and recommendations. Workshop materials are also included that are freely available on CD-ROM (all relevant PowerPoint presentations and manuals along with appropriate computer codes). (author)

  10. Workshop on nuclear structure and decay data: Theory and evaluation manual - Pt. 1

    International Nuclear Information System (INIS)

    Nichols, A.L.; McLaughlin, P.K.; p.mclaughlin@iaea.org

    2004-11-01

    A two-week Workshop on Nuclear Structure and Decay Data: Theory and Evaluation was organized and administrated by the IAEA Nuclear Data Section, and hosted at the Abdus Salam International Centre for Theoretical Physics (ICTP) in Trieste, Italy from 17 to 28 November 2003. The aims and contents of this workshop are summarized, along with the agenda, list of participants, comments and recommendations. Workshop materials are also included that are freely available on CD-ROM (all relevant PowerPoint presentations and manuals along with appropriate computer codes). (author)

  11. 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.

  12. BISERM version 2. Nuclear data library for evaluation of radiation effects in materials induced by neutrons of intermediate

    International Nuclear Information System (INIS)

    Korovin, Yu.A.; Stankovsky, A.Yu.; Konobeyev, A.Yu.; Pereslavtsev, P.E.

    1997-01-01

    This document describes the cross-section data library for studies of radiation effects induced by intermediate energy neutrons. The library contains hydrogen, helium-3 and helium-4 production cross-sections as well as nonelastic and total displacement cross-sections for neutrons in the energy range from threshold to 1 GeV. The cross-sections are given for 259 isotopes from 27 Al to 209 Bi. All this information is given in 18 compressed files plus one file with the catalogue of the data. The library was composed at the Institute of Nuclear Power Engineering in Obninsk, Russia. It is available on one PC diskette from the IAEA Nuclear Data Section costfree upon request. It requires 4 Mb of disk space after decompression. (author)

  13. Chinese computerized nuclear data library

    International Nuclear Information System (INIS)

    Liang Qichang; Cai Dunjiu

    1996-01-01

    The Second Version of Chinese Evaluated Nuclear Data Library (CENDL-2) includes the complete neutron nuclear data sets of 54 important elements and isotopes used for nuclear science and engineering with the incident neutron energy from 10 -5 eV to 20 MeV, the international universal format ENDF/B-6 was adopted. Now, the Chinese Computerized nuclear data library has been developed and put into operation. That is, the users can make on-line use of the main data libraries for evaluated neutron reaction data in the world of EXFOR experimental nuclear data library on the terminal of computer via the perfect computer software system, carry out directly the nuclear engineering calculation or nuclear data evaluation, enjoy the use of the resource of our nuclear data libraries for their development of nuclear energy and nuclear technology applications

  14. Estimation of covariance matrix on the experimental data for nuclear data evaluation

    International Nuclear Information System (INIS)

    Murata, T.

    1985-01-01

    In order to evaluate fission and capture cross sections of some U and Pu isotopes for JENDL-3, we have a plan for evaluating them simultaneously with a least-squares method. For the simultaneous evaluation, the covariance matrix is required for each experimental data set. In the present work, we have studied the procedures for deriving the covariance matrix from the error data given in the experimental papers. The covariance matrices were obtained using the partial errors and estimated correlation coefficients between the same type partial errors for different neutron energy. Some examples of the covariance matrix estimation are explained and the preliminary results of the simultaneous evaluation are presented. (author)

  15. Status of the JEFF nuclear data library

    International Nuclear Information System (INIS)

    Koning, A.J.; Bauge, E.; Dean, C.J.; Dupont, E.; Nordborg, C.; Rugama, Y.; Fischer, U.; Forrest, R.A.; Kellett, M.A.; Jacqmin, R.; Leeb, H.; Mills, R.W.; Pescarini, M.; Rullhusen, P.

    2011-01-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. Recently, the JEFF-3.1.1 nuclear data library was released and shortly after adopted by the French nuclear power industry for inclusion in their production and analysis codes. Recent updates include actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library, the decay data and fission yield sub-libraries, and fusion-related data files from the European F4E project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory, decay heat and shielding of thermal and fast systems. The next release of the library, JEFF-3.2, will be discussed. This will contain among others a significant increase of covariance data evaluations, modern evaluations for various structural materials, a larger emphasis on minor actinides and addition of high-quality gamma production data for many fission products. (authors)

  16. INDL/A - Suppl. 86/5. IAEA Nuclear Data Library for evaluated neutron reaction data of Actinides

    Energy Technology Data Exchange (ETDEWEB)

    Goulo, V G; Lemmel, H D; McLaughlin, P M [eds.

    1986-05-01

    This supplement to INDL/A contains five evaluations by V.A. Konshin on U-235 and Pu-239, 240, 241, 242. They are available upon request on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author) Refs, graphs

  17. INDL/A - Suppl. 86/5. IAEA Nuclear Data Library for evaluated neutron reaction data of Actinides

    International Nuclear Information System (INIS)

    Goulo, V.G.; Lemmel, H.D.; McLaughlin, P.M.

    1986-01-01

    This supplement to INDL/A contains five evaluations by V.A. Konshin on U-235 and Pu-239, 240, 241, 242. They are available upon request on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

  18. A modified Generalized Least Squares method for large scale nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Schnabel, Georg [Irfu, CEA, Université Paris-Saclay, 91191 Gif-sur-Yvette (France); Atominstitut, TU Wien, Vienna (Austria); Leeb, Helmut [Atominstitut, TU Wien, Vienna (Austria)

    2017-01-01

    Nuclear data evaluation aims to provide estimates and uncertainties in the form of covariance matrices of cross sections and related quantities. Many practitioners use the Generalized Least Squares (GLS) formulas to combine experimental data and results of model calculations in order to determine reliable estimates and covariance matrices. A prerequisite to apply the GLS formulas is the construction of a prior covariance matrix for the observables from a set of model calculations. Modern nuclear model codes are able to provide predictions for a large number of observables. However, the inclusion of all observables may lead to a prior covariance matrix of intractable size. Therefore, we introduce mathematically equivalent versions of the GLS formulas to avoid the construction of the prior covariance matrix. Experimental data can be incrementally incorporated into the evaluation process, hence there is no upper limit on their amount. We demonstrate the modified GLS method in a tentative evaluation involving about three million observables using the code TALYS. The revised scheme is well suited as building block of a database application providing evaluated nuclear data. Updating with new experimental data is feasible and users can query estimates and correlations of arbitrary subsets of the observables stored in the database.

  19. Status of the JEFF Nuclear Data Library

    International Nuclear Information System (INIS)

    Koning, A.J.; Bersillon, O.; Forrest, R. A.; Jacqmin, R.; Kellett, M.A.; Nouri, A.; Rullhusen, P.

    2005-01-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. The next version of the library, JEFF-3.1, comprises a significant update of actinide evaluations, evaluations emerging from European nuclear data projects, the activation library JEFF-3/A, the decay data and fission yield library, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities, or trends from integral experiments. Various pre-release validation efforts are underway, mainly for criticality and shielding of thermal and fast systems. This JEFF-3.1 library is expected to provide improved performances with respect to previous releases for a variety of scientific and industrial applications

  20. Status of the JEFF nuclear data library

    International Nuclear Information System (INIS)

    Koning, A.J.; Duijvestijn, M.C.; Bersillon, O.; Forrest, R.A.; Jacqmin, R.; Kellett, M.A.; Nouri, A.; Rullhusen, P.

    2005-03-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. The next version of the library, JEFF-3.1, comprises a significant update of actinide evaluations, evaluations emerging from European nuclear data projects, the activation library JEFF-3/A, the decay data and fission yield library, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities, or trends from integral experiments. Various pre-release validation efforts are underway, mainly for criticality and shielding of thermal and fast systems. This JEFF-3.1 library is expected to provide improved performances with respect to previous releases for a variety of scientific and industrial applications

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

    International Nuclear Information System (INIS)

    Murarka, I.P.

    1976-11-01

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

  2. Preparation of data for criticality safety evaluation of nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Okuno, Hiroshi; Suyama, Kenya; Yoshiyama, Hiroshi; Tonoike, Kotaro; Miyoshi, Yoshinori

    2005-01-01

    Nuclear Criticality Safety Handbook/Data Collection, Version 2 was submitted to the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan as a contract report. In this presentation paper, its outline and related recent works are presented. After an introduction in Chapter 1, useful information to obtain the atomic number densities was collected in Chapter 2. The nuclear characteristic parameters for 11 nuclear fuels were provided in Chapter 3, and subcriticality judgment graphs were given in Chapter 4. The estimated critical and estimated lower-limit critical values were supplied for the 11 nuclear fuels as results of calculations by using the Japanese Evaluated Nuclear Data Library, JENDL-3.2, and the continuous energy Monte Carlo neutron transport code MVP in Chapter 5. The results of benchmark calculations based on the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook were summarized into six fuel categories in Chapter 6. As for recent works, subcriticality judgment graphs for U-SiO 2 and Pu-SiO 2 were obtained. Benchmark calculations were made with the combination of the latest version of the library JENDL-3.3 and MVP code for a series of STACY experiments and the estimated critical and estimated lower-limit critical values of 10 wt%-enriched uranium nitrate solutions were calculated. (author)

  3. Development and benchmark analysis of the hybrid evaluated nuclear data library HENDL1.0

    International Nuclear Information System (INIS)

    Xu Dezheng; Wu Yican; Gao Chunjing; Zheng Shanliang; Li Jingjing; Zhu Xiaoxiang; Liu Haibo

    2004-01-01

    To meet the requirements of fusion-fission sub-critical hybrid reactor design and the other related studies, the evaluate nuclear data library named HENDL1.0/E has been constituted based on the several main national evaluated data libraries. The relevant working libraries including transport sub-libraries HENDL1.0/MG in groupwise form, HENDL1.0/MC in pointwise form, and the burnup sub-library HENDL1.0/BU and response function sub-library HENDL1.0/RF are generated using the nuclear data processing codes NJOY97 and TRANSX2. The simulating calculation and comparative analysis are carried out against a series of existing benchmark test experiments with popular neutron transport codes, in order to validate the correctness and availability of the HENDL1.0. (authors)

  4. Working Party on International Nuclear Data Evaluation Cooperation (WPEC). Presentations and documents submitted to the 25. meeting, NEA Headquarters, 23-24 May 2013

    International Nuclear Information System (INIS)

    2013-01-01

    ; - Subgroup 38: A modern nuclear database structure beyond the ENDF format (slides + report); Presentations for the following new subgroup proposals are available: - Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files; CIELO (Collaborative International Evaluated Library Organization). A reminder of the main guidelines of the Method of Work is given as well as information about the current WPEC mandate and its 2013-2016 renewal

  5. Proceedings of the 2005 symposium on nuclear data

    International Nuclear Information System (INIS)

    Tahara, Yoshihisa; Fukahori, Tokio

    2006-11-01

    The 2005 Symposium on Nuclear Data was held at Nuclear Science Research Institute in Tokai Research and Development Center, Japan Atomic Energy Agency (JAEA), on 2nd and 3rd of February 2006. Japanese Nuclear Data Committee and Nuclear Data Center, JAEA organized this symposium. In the oral sessions, presented were 16 papers on topics of nuclear data for the innovative reactor development and upgrade of current light water reactor, the past and future of nuclear data research, capability of the latest evaluated nuclear data files, and recent cross section measurements. In the poster session, presented were 21 papers concerning experiments, evaluations, benchmark tests, applications and so on. A part of those presented papers are compiled in this proceedings. The 36 of the presented papers are indexed individually. (J.P.N.)

  6. Integrated system for production of neutronics and photonics calculational constants. Volume 17, Part B, Rev. 1. Program SIGMA 1 (Version 78-1): Doppler broadened evaluated cross sections in the evaluated nuclear data file/Version B (ENDF/B) format. [For CDC-7600

    Energy Technology Data Exchange (ETDEWEB)

    Cullen, D.E.

    1978-07-04

    The code SIGMA1 Doppler broadens evaluated cross sections in the ENDF/B format. The code can be applied only to data that vary as a linear function of energy and cross section between tabulated points. This report describes the methods used in the code and serves as a user's guide to the code. 6 figures, 2 tables.

  7. Integrated system for production of neutronics and photonics calculational constants. Volume 17, Part B, Rev. 1. Program SIGMA 1 (Version 78-1): Doppler broadened evaluated cross sections in the evaluated nuclear data file/Version B (ENDF/B) format

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1978-01-01

    The code SIGMA1 Doppler broadens evaluated cross sections in the ENDF/B format. The code can be applied only to data that vary as a linear function of energy and cross section between tabulated points. This report describes the methods used in the code and serves as a user's guide to the code. 6 figures, 2 tables

  8. Covariance methods and practices in the field of nuclear data

    International Nuclear Information System (INIS)

    Piksaikin, V.

    1988-01-01

    This document contains the 14 invited papers presented at the quoted meeting and summarizes the conclusions and recommendations that arose from the discussions during this meeting. Special emphasis was given to the treatment of correlated neutron nuclear data in fission and fusion reactor applications including computations related to neutron dosimetry and neutron spectra, fission-product yield data, and evaluated nuclear data files. (author). Refs, figs and tabs

  9. Clustering of experimental data and its application to nuclear data evaluation

    International Nuclear Information System (INIS)

    Abboud, A.; Rashed, R.; Ibrahim, M.

    1997-01-01

    A semi-automatic pre-processing technique has been proposed by Iwasaki to classify the experimental data for a reaction into one or a small number of large data groups, called main cluster(s), and to eliminate some data which deviate from the main body of the data. The classifying method is based on a technique like pattern clustering in the information processing domain. Test of the data clustering formed reasonable main clusters for three activation cross-sections. This technique is a helpful tool in the neutron cross-section evaluation. (author). 4 refs, 1 fig., 3 tabs

  10. Clustering of experimental data and its application to nuclear data evaluation

    International Nuclear Information System (INIS)

    Abboud, A.; Rashed, R.; Ibrahim, M.

    1998-01-01

    A semi-automatic pre-processing technique has been proposed by Iwasaki to classify the experimental data for a reaction into one or a small number of large data groups, called main cluster (s), and to eliminate some data which deviates from the main body of the data. The classifying method is based on technique like pattern clustering in the information processing domain. Test of the data clustering formed reasonable main clusters for three activation cross-sections. This technique is a helpful tool in the neutron cross-section evaluation

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

    International Nuclear Information System (INIS)

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

    1984-12-01

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

  12. 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)

  13. Reactor fuel performance data file, 1985 edition

    International Nuclear Information System (INIS)

    Harayama, Yasuo; Fujita, Misao; Watanabe, Kohji.

    1986-07-01

    In safety evaluation and integrity studies of reactor fuel, data on fuel performance are the most basic materials. The Fuel Reliability Laboratory No.1 has obtained the fuel performance data by joining in some international programs to study the safety and integrity of fuel. Those data have only used for the studies in the above two fields. However, if the data are rearranged and compiled in a easily usable form, they can be utilized in other field of studies. Then, a 'data file' on fuel performance is beeing compiled by adding data from open literatures to those obtained in international programs. The present report is prepared on the basis of the data file compiled by March in 1986. (author)

  14. Evaluation of beta intensity data in nuclear decay schemes: Comments on some pitfalls

    International Nuclear Information System (INIS)

    Reich, C.W.

    1987-02-01

    Some of the problems that arise in the evaluation of decay-schemes data to obtain values for the intensities of beta transitions are discussed. As examples of these problems, the decay schemes of 87 Br and 233 Pa are examined. No specific solutions to these problems are offered; but by pointing out to the participants in the International Nuclear Structure and Decay Data Evaluation Network, and to others, it is hoped that a general understanding of them can be gained, which may ultimately lead to a consistent means of dealing with them. 14 refs., 2 figs

  15. Evaluation of neutron nuclear data of natural calcium for CENDL-1

    International Nuclear Information System (INIS)

    Tang Gouyou; Bao Shanglian; Shi Zhaomin; Cao Wentian

    1989-03-01

    Neutron nuclear data of natural calcium for CENDL-1 has been evaluated in the energy region from 10 -5 ev to 20 MeV. Evaluated quantities are the total, non-elastic scattering, elastic and inelastic scattering, radiation capture, (n,p), (n,t), (n,2n), (n,a) reaction cross sections and the angular distributions of elastic and inelastic cross sections. Some of the data were calculated with the program AUJP based on the optical model and the program MUP2 based on the Hauser-Feshbach model and pre-equilibrium evaporation model. (author). 34 refs, 8 figs, 3 tabs

  16. Evaluation of β intensity data in nuclear decay schemes: comments on some pitfalls

    International Nuclear Information System (INIS)

    Reich, C.W.

    1986-01-01

    Some of the problems which arise in the evaluation of decay-schemes data to obtain values for the intensities of β transitions are discussed. As examples of these problems, the decay schemes of 87 Br and 233 Pa are examined. No specific solutions to these problems are offered; but by pointing them out to the participants in the International Nuclear Structure and Decay Data Evaluation Network, it is hoped that a general understanding of them can be gained, which may ultimately lead to a consistent means of dealing with them. 14 refs., 2 figs., 1 tab

  17. LLNL nuclear data libraries used for fusion calculations

    International Nuclear Information System (INIS)

    Howerton, R.J.

    1984-01-01

    The Physical Data Group of the Computational Physics Division of the Lawrence Livermore National Laboratory has as its principal responsibility the development and maintenance of those data that are related to nuclear reaction processes and are needed for Laboratory programs. Among these are the Magnetic Fusion Energy and the Inertial Confinement Fusion programs. To this end, we have developed and maintain a collection of data files or libraries. These include: files of experimental data of neutron induced reactions; an annotated bibliography of literature related to charged particle induced reactions with light nuclei; and four main libraries of evaluated data. We also maintain files of calculational constants developed from the evaluated libraries for use by Laboratory computer codes. The data used for fusion calculations are usually these calculational constants, but since they are derived by prescribed manipulation of evaluated data this discussion will describe the evaluated libraries

  18. Activity report of Japanese Nuclear Data Committee in period of April 1993 to March 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This is a progress report on the activities of the Japanese Nuclear Data Committee (JNDC) in the period of April 1993 to March 1995. In this period, the latest version of the Japanese Evaluated Nuclear Data Library, JENDL-3.2, has been released for users after benchmark tests of data therein. Preparation of the special purpose nuclear data files has been also progressed. As special topics, the followings are presented here : (1) the completion and benchmark tests of the JENDL-3.2, (2) progress in evaluating special purpose nuclear data, (3) progress in studying high energy nuclear data, and (4) utilization of nuclear data by means of internet. (author)

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

    International Nuclear Information System (INIS)

    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

  20. JENDL FP decay data file 2000 and the beta-decay theory

    International Nuclear Information System (INIS)

    Yoshida, Tadashi; Katakura, Jun Ichi; Tachibana, Takahiro

    2002-01-01

    JENDL FP Decay Data File 2000 has been developed as one of the special purpose files of the Japanese Evaluated Nuclear Data Library (JENDL), which constitutes a versatile nuclear data basis for science and technology. In the format of ENDF-6 this file includes the decay data for 1087 unstable fission product (FP) nuclides and 142 stable nuclides as their daughters. The primary purpose of this file is to use in the summation calculation of FP decay heat, which plays a critical role in nuclear safety analysis; the loss-of-coolant accident analysis of reactors, for example. The data for a given nuclide are its decay modes, the Q value, the branching ratios, the average energies released in the form of beta- and gamma-rays per decay, and their spectral data. The primary source of the decay data adopted here is the ENSDF (Evaluated Nuclear Structure Data File). The data in ENSDF, however, cover only the measured values. The data of the short-lived nuclides, which are essential for the decay heat calculations at short cooling times, are often fully lacking or incomplete even if they exist. This is mainly because of their short half-life nature. For such nuclides a theoretical model calculation is applied in order to fill the gaps between the true and the experimentally known decay schemes. In practice we have to predict the average decay energies and the spectral data for a lot of short-lived FPs by use of beta-decay theories. Thus the beta-decay theory plays a very important role in generating the FP decay data file

  1. Nuclear data newsletter. No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-03-01

    This issue describes the ENDF/B-5 nuclear data library format which can be considered as the international format for the exchange of evaluated neutron reaction data. It lists the new nuclear data libraries recently received by the Nuclear Data Section of the IAEA, as well as a selection of new relevant documents.

  2. ENSL and CDRL: Evaluated nuclear structure libraries

    International Nuclear Information System (INIS)

    Howerton, R.J.

    1981-01-01

    Two files of nuclear structure data derived largely from the seventh edition of the Table of Isotopes are described. The files are computer oriented, and have been constructed to so that every decay can be traced either to an eventual ground state of to a positive flag that indicates nothing is known about further decay. The ENSL file contains level schemes derived from decay data, and the CDRL file contains the level schemes derived from particle-induced reaction data that have been merged into the ENSL file. (author)

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

    International Nuclear Information System (INIS)

    Abriola, D.; Dimitriou, P.; Ricard-McCutchan, E.; Tuli, J.K.

    2013-08-01

    Biennial meetings of the International Network of Nuclear Structure and Decay Data (NSDD) evaluators are held under the auspices of the IAEA. The Network 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 are included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS). The results represent the recommended 'best values' for the various nuclear structure and decay data properties. These data and bibliographic details are also available through the World Wide Web, CD-ROM, wall charts of the nuclides, Nuclear Wallet Cards and other such media. The US efforts are coordinated by the Coordinating Committee of the US Nuclear Data Program. The ENSDF master database is maintained by the US National Nuclear Data Centre at Brookhaven National Laboratory, and these data are also available from other distribution centres including the IAEA Nuclear Data Section. Biennial meetings of the Network are sponsored by the IAEA Nuclear Data Section, and have the following objectives: (a) coordination of the work of all centres and groups participating in the compilation, evaluation and dissemination of NSDD; (b) maintenance of and improvements to the standards and rules governing NSDD evaluations; (c) review of the development and common use of computerized systems and databases maintained specifically for this activity. In those meetings detailed studies and discussions are undertaken over a five-day period. This document represents a summary of the Network meeting held at the Kuwait Foundation for the Advancement of Sciences (KFAS), Safat, Kuwait, from 27 to 31 January 2013. Thirty-six nuclear data specialists from seventeen countries attended this meeting to

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

    Energy Technology Data Exchange (ETDEWEB)

    Abriola, D.; Dimitriou, P. [IAEA Nuclear Data Section, Vienna (Austria); Ricard-McCutchan, E.; Tuli, J. K. [Brookhaven National Laboratory, Upton, NY (United States)

    2013-08-15

    Biennial meetings of the International Network of Nuclear Structure and Decay Data (NSDD) evaluators are held under the auspices of the IAEA. The Network 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 are included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS). The results represent the recommended 'best values' for the various nuclear structure and decay data properties. These data and bibliographic details are also available through the World Wide Web, CD-ROM, wall charts of the nuclides, Nuclear Wallet Cards and other such media. The US efforts are coordinated by the Coordinating Committee of the US Nuclear Data Program. The ENSDF master database is maintained by the US National Nuclear Data Centre at Brookhaven National Laboratory, and these data are also available from other distribution centres including the IAEA Nuclear Data Section. Biennial meetings of the Network are sponsored by the IAEA Nuclear Data Section, and have the following objectives: (a) coordination of the work of all centres and groups participating in the compilation, evaluation and dissemination of NSDD; (b) maintenance of and improvements to the standards and rules governing NSDD evaluations; (c) review of the development and common use of computerized systems and databases maintained specifically for this activity. In those meetings detailed studies and discussions are undertaken over a five-day period. This document represents a summary of the Network meeting held at the Kuwait Foundation for the Advancement of Sciences (KFAS), Safat, Kuwait, from 27 to 31 January 2013. Thirty-six nuclear data specialists from seventeen countries attended this meeting to

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

    International Nuclear Information System (INIS)

    Riemer, R.L.

    1992-01-01

    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

  6. Compilation of requests for nuclear data

    International Nuclear Information System (INIS)

    1981-03-01

    A request list for nuclear data which was produced from a computerized data file by the National Nuclear Data Center is presented. The request list is given by target nucleus (isotope) and then reaction type. The purpose of the compilation is to summarize the current needs of US Nuclear Energy programs and other applied technologies for nuclear data. Requesters are identified by laboratory, last name, and sponsoring US government agency

  7. Evaluation of neutron nuclear data of 241pu for JENDL-2

    International Nuclear Information System (INIS)

    Kikuchi, Yasuyuki; Sekine, Nobuo

    1984-06-01

    Neutron nuclear data of 241 Pu were newly evaluated for JENDL-2. Evaluated quantities are the total, elastic and inelastic scattering, fission, capture, (n,2n), (n,3n) and (n,4n) reaction cross sections, the resolved and unresolved resonance parameters, the angular and energy distributions of emitted neutrons, and the average number of neutrons emitted per fission. The simultaneous evaluation method was adopted for the fission cross section so as to keep the consistency among the main fissile and fertile material nuclides. The theoretical calculations based on the spherical optical model and the statistical model were also used, when the experimental data were not sufficient. Discussion is given on the evaluation method. (author)

  8. OVERVIEW OF THE 2009 RELEASE OF THE EVALUATED NUCLEAR DATA LIBRARY (ENDL2009)

    International Nuclear Information System (INIS)

    Brown, D.A.; Beck, B.; Descalle, M.; Hoffman, R.; Ormand, E.; Navratil, P.; Summers, N.; Thompson, I.; Vogt, R.; Younes, W.; Barnowski, R.

    2010-01-01

    The Lawrence Livermore National Laboratory (LLNL) Physics Division has produced the next iteration of LLNL's evaluated nuclear database, ENDL2009. ENDL2009 is the second in a series of major ENDL library releases designed to support LLNL's current and future nuclear data needs. This library includes 585 distinct transport-ready evaluations in the neutron sub-library and many physics improvements for stockpile stewardship, attribution signatures, key radiochemical diagnostics and performance of conventional and hybrid fission/fusion reactors. In building this library, we adopted the best of the world's nuclear data efforts: 46% of the library is from the ENDF/B-VII.0 library, 10% is from the JENDL libraries and 8% from other libraries. The remaining 36% of the neutron sub-library and all of the charged-particle sub-libraries consist of new evaluations developed at LLNL for the ENDL2009 library. In addition, ENDL2009 supports new features such as energy-dependent Q values from fission, support for unresolved resonances and average momentum deposition. Finally, this release is our most highly tested release as we have strengthened our already rigorous testing regime by adding tests against LANL Activation Ratio Measurements and more than 1200 new critical assemblies. Our testing is now being incorporated into our development process and is serving to guide database improvements.

  9. Evaluation of neutron nuclear data for 241Am and 243Am

    International Nuclear Information System (INIS)

    Kikuchi, Yasuyuki

    1982-08-01

    Neutron nuclear data of 241 Am and 243 Am were evaluated for JENDL-2. Evaluated quantities are the total, elastic and inelastic scattering, fission, capture, (n,2n), (n,3n) and (n,4n) reaction cross sections, the resolved and unresolved resonance parameters, the angular or energy distribution of the emitted neutrons, and the average number of neutrons emitted per fission. The fission cross section was evaluated on the basis of newly measured data, and lower values than JENDL-1 were given in the subthreshold energy region. The reliability of the calculation parameters are also much improved, because experimental data became available for the total and capture cross sections of 241 Am in the high energy region. (author)

  10. Report to the US Nuclear Regulatory Commission on Analysis and Evaluation of Operational Data, 1987: Nonreactors

    International Nuclear Information System (INIS)

    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 nonreactor 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

  11. Evaluation of the fusion-related neutron nuclear data for JENDL-3

    International Nuclear Information System (INIS)

    Chiba, Satoshi

    1988-01-01

    Status of the neutron nuclear data evaluations for JENDL-3 will be described for nuclides important in the development of D-T fusion reactors. In this article, however, only explanation of the evaluations for the very light mass region will be presented to avoid overlapping with what are given in another papers submitted to this seminar. Emphases are placed on the tritium production cross sections, inelastic scattering cross sections including the double-differential neutron emission spectrum (DDX), threshold reaction cross sections and photon production cross sections. The methods employed to prepare JENDL-3T library and their results will be summarized. (author)

  12. Nuclear data newsletter. No. 2

    International Nuclear Information System (INIS)

    1980-10-01

    This issue contains bibliographic data describing: neutron nuclear data (CINDA); charged particle reaction data; experimental nuclear reaction data; evaluated nuclear data library (ENDF/B); libraries in formats other than ENDF/B, such as BOSPOR-78 (evaluated data for threshold neutron reactions), SOKRATOR (new USSR evaluations), INDL/A (IAEA nuclear data library for actinides). It includes the following descriptions of the recently received libraries: DAMSIG-77, DOCROS-77, JUELGAM-79, GSI gamma-ray library, KEDAK-3, PNESD, UKNDL-80, etc. A summary description and documentation of the multigroup cross section data libraries which exist at the IAEA is cited and new documents of interest are listed

  13. Nuclear data newsletter. No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-10-01

    This issue contains bibliographic data describing: neutron nuclear data (CINDA); charged particle reaction data; experimental nuclear reaction data; evaluated nuclear data library (ENDF/B); libraries in formats other than ENDF/B, such as BOSPOR-78 (evaluated data for threshold neutron reactions), SOKRATOR (new USSR evaluations), INDL/A (IAEA nuclear data library for actinides). It includes the following descriptions of the recently received libraries: DAMSIG-77, DOCROS-77, JUELGAM-79, GSI gamma-ray library, KEDAK-3, PNESD, UKNDL-80, etc. A summary description and documentation of the multigroup cross section data libraries which exist at the IAEA is cited and new documents of interest are listed.

  14. Working Party on International Nuclear Data Evaluation Co-operation (WPEC). Presentations and documents submitted to the 28. meeting, OECD Headquarters, Conference Centre, Paris, France, 9-13 May 2016

    International Nuclear Information System (INIS)

    2016-05-01

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countries) and CENDL (China) in close co-operation with the Nuclear Data Section of the International Atomic Energy Agency (IAEA). The working party was established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, validation, and related topics, and to provide a framework for co-operative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint evaluation and/or measurement efforts. The 28. Meeting of the WPEC was the occasion to review the experimental activities, the evaluation projects and the Status of subgroups. This document brings together the available documents of the meeting: 1 - The Reports on experimental activities: Europe (NEA DB), Japan, USA, China; 2 - Some Brief progress reports from the evaluation projects: ENDF, JEFF, JENDL, BROND/ROSFOND, CENDL, IAEA, TENDL; 3 - The Status of subgroups: Subgroup 37 (Improved fission product yield evaluation methodologies); Subgroup 38 (A modern nuclear database structure beyond the ENDF format); Subgroup 39 (Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files); Subgroup 40 (Collaborative International Evaluated Library Organisation (CIELO) Pilot Project); Subgroup 41 (Improving nuclear data accuracy of 241 Am and 237 Np capture cross-sections); Subgroup 42 (Thermal Scattering Kernel S(a,b): Measurement, Evaluation and Application); Subgroup C (High Priority Request List - HPRL); New Subgroups were proposed and presented: 43 - Code infrastructure to support a general nuclear database structure; WPEC long-term sub-group proposal: International standard for a general nuclear database structure

  15. The method to set up file-6 in neutron data library of light nuclei below 20 MeV

    International Nuclear Information System (INIS)

    Zhang Jingshang; Han Yinlu

    2001-01-01

    So far there is no file-6 (double differential cross section data, DDX) of the light nuclei in the main evaluated neutron nuclear data libraries in the world. Therefore, locating a proper description on the double differential cross section of all kinds of outgoing particles from neutron induced light nucleus reaction below 20 MeV is necessary. The motivation for this work is to introduce a way to set up file-6 in the neutron data library

  16. 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.

  17. 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.

  18. Nuclear reaction data and nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Paver, N [University of Trieste (Italy); Herman, M [International Atomic Energy Agency, Vienna (Austria); Gandini, A [ENEA, Rome (Italy)

    2001-12-15

    These two volumes contain the lecture notes of the workshop 'Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety', which was held at the Abdus Salam ICTP in the Spring of 2000. The workshop consisted of five weeks of lecture courses followed by practical computer exercises on nuclear data treatment and design of nuclear power systems. The spectrum of topics is wide enough to timely cover the state-of-the-art and the perspectives of this broad field. The first two weeks were devoted to nuclear reaction models and nuclear data evaluation. Nuclear data processing for applications to reactor calculations was the subject of the third week. On the last two weeks reactor physics and on-going projects in nuclear power generation, waste disposal and safety were presented.

  19. Progress in fission product nuclear data. Information about activities in the field of measurements and compilations/evaluations of fission product nuclear data (FPND)

    International Nuclear Information System (INIS)

    Lammer, G.

    1978-07-01

    This is the fourth issue of a report series on Fission Product Nuclear Data (FPND) which is published by the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). The purpose of this series is to inform scientists working on FPND, or using such data, about all activities in this field which are planned, ongoing, or have recently been completed. The main part of this report consists of unaltered original contributions which the authors have sent to IAEA/NDS. The types of activities being included in this report are measurements, compilations and evaluations of: Fission product yields (neutron induced and spontaneous fission); neutron reaction cross sections of fission products; data related to the radioactive decay of fission products; delayed neutron data of fission products; and lumped fission product data (decay heat, absorption etc.)

  20. Evaluation of corrective action data for reportable events at commercial nuclear power plants

    International Nuclear Information System (INIS)

    Mays, G.T.

    1991-01-01

    805The Nuclear Regulatory Commission (NRC) approved the adoption of cause codes for reportable events as a new performance indicator (PI) in March 1989. Corrective action data associated with the causes of events were to be compiled also. The corrective action data was considered as supplemental information but not identified formally as a performance indicator. In support of NRC, the Nuclear Operations Analysis Center (NOAC) at the Oak Ridge National Laboratory (ORNL) has been routinely evaluating licensee event reports (LERs) for cause code and corrective action data since 1989. The compilation of corrective action data by NOAC represents the first systematic and comprehensive compilation of this type data. The thrust of analyzing the corrective action data was to identify areas where licensees allocated resources to solve problems and prevent the recurrence of personnel errors and equipment failures. The predominant areas of corrective action reported by licensees are to be evaluated by NRC to compare with NRC programs designed to improve plant performance. The set of corrective action codes used to correlate with individual cause codes and included in the analyses were: training, procedural modification, corrective discipline, management change, design modification, equipment replacement/adjustment, other, and unknown. 1 fig

  1. Evaluated Nuclear Data Library for Transport Calculations at Energies up to 150 MeV

    International Nuclear Information System (INIS)

    Korovin, Yu.A.; Konobeyev, A.Yu.; Pilnov, G.B.; Stankovskiy, A.Yu.

    2005-01-01

    A new evaluated nuclear data library has been created. The library consists of two sub-libraries for neutron and proton incident particles. The first version of neutron sub-library has been completed and described in the present paper. The library contains nuclear data for transport, heating, and shielding applications for 242 nuclides ranging in atomic number from 8 to 82 in the energy region of primary neutrons from 10-5 eV to 150 MeV. Data below 20 MeV are taken mainly from ENDF/B-VI (Revision 8) and for some nuclides, from the JENDL-3.3 and JEFF-3.0 libraries. The evaluation of emitted particle energy and angular distributions at the energies above 20 MeV was performed with the help of the ALICE/ASH code and the analysis of available experimental data. The total cross sections, elastic cross sections, and elastic scattering angular distributions were calculated with the help of the coupled channel model. The results of the calculation were adjusted to the data from ENDF/B-VI, JENDL-3.3m or JEFF-3.0 at the neutron energy equal to 20 MeV. The library is written in ENDF/B-VI format using the MF=3/MT=5 and MF=6/MT=5 representations

  2. Nuclear-data evaluation based on direct and indirect measurements with general correlations

    International Nuclear Information System (INIS)

    Muir, D.W.

    1988-01-01

    Optimum procedures for the statistical improvement, or updating, of an existing nuclear-data evaluation are reviewed and redeveloped from first principles, consistently employing a minimum-variance viewpoint. A set of equations is derived which provides improved values of the data and their covariances, taking into account information from supplementary measurements and allowing for general correlations among all measurements. The minimum-variance solutions thus obtained, which we call the method of 'partitioned least squares,' are found to be equivalent to a method suggested by Yu. V. Linnik and applied by a number of authors to the analysis of fission-reactor integral experiments; however, up to now, the partitioned-least-squares formulae have not found widespread use in the field of basic data evaluation. This approach is shown to give the same results as the more commonly applied Normal equations, but with reduced matrix inversion requirements. Examples are provided to indicate potential areas of application. (author)

  3. Evaluation of environmental data relating to selected nuclear power plant sites. Kewaunee Nuclear Power Plant site

    International Nuclear Information System (INIS)

    Murarka, I.P.; Ferrante, J.G.; Policastro, A.J.; Daniels, E.W.

    1976-08-01

    Environmental monitoring data for the years 1973, 1974 and 1975 pertaining to the Kewaunee Plant, which began operation in mid-1974, were analyzed by qualitative and quantitative methods. 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 prediction that any are developing. The data acquired, method of analysis, and results obtained are presented in detail along with recommendations for improving monitoring techniques

  4. ENDL-84. The Evaluated Nuclear Data Library of the Lawrence Livermore National Laboratory in the ENDF-5 format

    International Nuclear Information System (INIS)

    Cullen, D.E.; McLaughlin, P.K.; Lemmel, H.D.

    1990-09-01

    This document summarizes the contents of the evaluated nuclear data library (ENDL) by the Lawrence Livermore National Laboratory, USA, converted to ENDF-5 format. The library contains evaluated data for all significant neutron reactions in the energy range from 10 -4 eV to 20 MeV for 94 elements or isotopes. The entire library or selective retrievals from it can be obtained on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

  5. Neutron nuclear data evaluation of cesium isotopes for JENDL-4.0

    International Nuclear Information System (INIS)

    Iwamoto, Nobuyuki

    2011-01-01

    For the development of JENDL-4.0, neutron nuclear data for fission product nuclides, 133,134,135,136,137 Cs, were revised in the incident neutron energy range from 1 eV to 20 MeV by using a coupled-channels optical model (OM), and nuclear reaction models. The OM potential parameters were determined for stable 133 Cs to reproduce the experimental data of total and elastic scattering cross sections and angular distributions of elastically scattered neutrons. The present results reasonably reproduce measured data for (n,2n), (n,p), (n,α), and capture reactions on 133 Cs. Important differences between the present results and JENDL-3.3 are found for the capture cross sections of 134,137 Cs. The cross section obtained for 137 Cs was smaller than that in JENDL-3.3. This result makes the transmutation of medium-lived 137 Cs increasingly difficult. The production probabilities of metastable states for 134,138 Cs via capture reactions on 133,137 Cs are compared with experimental values. The present result for 134m Cs production is marginally consistent with measured data. However, a large discrepancy is recognized for 138m Cs production. The γ-ray emission data were evaluated with available measurements, and newly compiled in JENDL-4.0. Maxwellian-averaged capture cross sections were calculated in the energy range from 1 to 10 3 keV, and are compared with other derived data. (author)

  6. Nuclear Data Sheets for A = 81

    International Nuclear Information System (INIS)

    Baglin, Coral M.

    2008-01-01

    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 81 Y (literature cutoff 8 October 1998) and 81 Zr (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 81 Ga, and knowledge of excited state properties for 81 Y and 81 Zr has been significantly expanded. However, the expected ε+β + decay of 81 Zr has yet to be studied

  7. The FOND-2.2 evaluated neutron data library (Russian library of evaluated neutron data files for generating sets of constants in the ABBN constants system)

    International Nuclear Information System (INIS)

    Koshcheev, V.N.; Nikolaev, M.N.; Korchagina, Zh.A.; Savoskina, G.V.

    2001-01-01

    A short description is given of the Russian evaluated neutron data library FOND-2.2. The main purpose of FOND-2.2 is to provide sets of constants for the ABBN constants system. A history of its compilation and the sources of the neutron data are given. The contents of FOND-2.2 are presented with brief comments. (author)

  8. Assistance system for nuclear data evaluation in an object-oriented environment

    International Nuclear Information System (INIS)

    Iwasaki, S.; Odano, N.; Sugiyama, K.

    1994-01-01

    An object-oriented framework for an assistance system for neutron nuclear data evaluation has been proposed, and an assisting system for theoretical model fitting to the experimental data has been developed. In the model fitting procedure, we employed a method based on the general least-squares technique. Almost all things appearing in the process were easily and naturally modeled by objects in this environment. The objects can also be connected by a set of rules either with other objects, with the existing or newly developed external processes and with data bases. In total twelve sub-processes were supported by each knowledge base. As an example of the fitting procedure the case of 59 Co as the target nuclide is presented. (Author)

  9. Twenty-Fourth Meeting of the Working Party on International Nuclear Data Evaluation Co-operation, 24-25 May 2012, NEA Headquarters, 12 boulevard des Iles, 92130 Issy-les-Moulineaux, France - Summary record

    International Nuclear Information System (INIS)

    2013-01-01

    This paper gives the summary record of the past 24. Meeting of the Working Party on International Nuclear Data Evaluation Co-operation: review of the experimental nuclear data activities of relevance to the evaluation projects (NEA Data Bank member countries, Japan, USA, China, Russia), brief progress reports from the evaluation projects and discussion of future plans (ENDF, JEFF, JENDL, TENDL, BROND, CENDL, IAEA), review of final or near-final subgroup reports (subgroups 27 (Prompt photon production from fission products), 28 (Processing of covariance data), 29 (U-235 capture cross-section in the keV to MeV energy region), 31 (Meeting nuclear data needs for advanced reactor systems)), status of ongoing subgroups (subgroups C (High priority request list for nuclear data), 33 (Methods and issues for the combined use of integral experiments and covariance), 34 (Coordinated evaluation of 239 Pu in the resonance region), 35 (Scattering angular distribution in the fast energy range), 36 (Reporting and usage of experimental data for evaluation in the resolved resonance region)), proposals for new subgroups, discussions on the opportunity to create a World Wide Evaluated Nuclear Data File/Library, information on conferences and meetings of interest to the nuclear data community

  10. Report on the IAEA coordinated research programme on the intercomparison of evaluations of actinide neutron nuclear data

    International Nuclear Information System (INIS)

    Yiftah, S.

    1979-03-01

    Following discussions and Consultants Meeting in 1976, the IAEA, in response to recommendations made formed two coordinated research projects (CRP): one on the Intercomparison of Evaluations of Actinide Neutron Nuclear Data, the other on the Measurement and Evaluation of Transactinium Isotope Nuclear Decay Data. This report covers work done, and to be done, in the framework of the first CRP, as well as some of the practical problems for future work. (B.G.)

  11. Nuclear energy data

    International Nuclear Information System (INIS)

    1990-01-01

    Nuclear Energy Data is the OECD Nuclear Energy Agency's annual compilation of basic statistics on electricity generation and nuclear power in OECD countries. The reader will find quick and easy reference to the present status of and projected trends in total electricity generating capacity, nuclear generating capacity, and actual electricity production as well as on supply and demand for nuclear fuel cycle services [fr

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

    International Nuclear Information System (INIS)

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

    1994-11-01

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

  13. 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.

  14. The role and importance of the use and development of applied nuclear theory and computer codes for neutron nuclear data evaluation in the developing countries

    International Nuclear Information System (INIS)

    Mehta, M.K.

    1976-01-01

    The situation in developing countries is reviewed first by examining the motivation for such work and then by setting up a few criteria necessary for carrying out data evaluation programmes. The case for one country-India is discussed in detail under these criteria and general inferences are drawn from this. Recommendations are made based on this review to bring about interactions between the basic nuclear theorists and nuclear data evaluation groups in developing countries. (author)

  15. Evaluation of neutron nuclear data of 9Be for JENDL-3

    International Nuclear Information System (INIS)

    Shibata, Keiichi

    1984-12-01

    Neutron nuclear data of 9 Be have been evaluated for JENDL-3 in the energy range from 10 -5 eV to 20 MeV. Evaluated quantities are the total, elastic and inelastic scattering, photon-production, (n,γ), (n,p), (n,d), (n,t) and (n,α) reaction cross sections and the angular and energy distributions of neutrons. The total cross section below 830 keV was calculated with the R-matrix theory. The statistical model was applied to the prediction of the inelastic scattering and charged-particle emission cross sections. The (n,2n) reaction cross section is given by the sum of the inelastic scattering and (n,α 1 ) reaction cross sections. (author)

  16. The role of nuclear data for fusion technology studies

    International Nuclear Information System (INIS)

    Forrest, Robin A.

    2011-01-01

    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.

  17. ENSL and CDRL: evaluated nuclear structure libraries

    International Nuclear Information System (INIS)

    Howerton, R.J.

    1981-01-01

    Two files of nuclear structure data derived largely from the seventh edition of the Table of Isotopes are described. The files are computer oriented, and have been constructed so that every decay can be traced either to an eventual ground state or to a positive flag that indicates nothing is known about further decay. 1 table

  18. Nuclear data newsletter. No. 5

    International Nuclear Information System (INIS)

    1983-05-01

    This issue lists the new nuclear data libraries received by the IAEA Nuclear Data Section: ENDL-98; ACTL-82; ECPL-82; ENDF/B-4; IAEA Evaluated Neutron data Library (INDL); INDL/F-83; and the data handling pre-processing codes. It announces available charts of nuclides and also lists a selection of new relevant documents

  19. 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

  20. Nuclear structure and radioactive decay resources at the US National Nuclear Data Center

    International Nuclear Information System (INIS)

    Sonzogni, A.A.; Burrows, T.W.; Pritychenko, B.; Tuli, J.K.; Winchell, D.F.

    2008-01-01

    The National Nuclear Data Center has a long tradition of evaluating nuclear structure and decay data as well as offering tools to assist in nuclear science research and applications. With these tools, users can obtain recommended values for nuclear structure and radioactive decay observables as well as links to the relevant articles. The main databases or tools are ENSDF, NSR, NuDat and the new Endf decay data library. The Evaluated Nuclear Structure Data File (ENSDF) stores recommended nuclear structure and decay data for all nuclei. ENSDF deals with properties such as: -) nuclear level energies, spin and parity, half-life and decay modes, -) nuclear radiation energy and intensity for different types, -) nuclear decay modes and their probabilities. The Nuclear Science References (NSR) is a bibliographic database containing nearly 200.000 nuclear sciences articles indexed according to content. About 4000 are added each year covering 80 journals as well as conference proceedings and laboratory reports. NuDat is a software product with 2 main goals, to present nuclear structure and decay information from ENSDF in a user-friendly way and to allow users to execute complex search operations in the wealth of data contained in ENSDF. The recently released Endf-B7.0 contains a decay data sub-library which has been derived from ENSDF. The way all these databases and tools have been offered to the public has undergone a drastic improvement due to advancements in information technology

  1. Fourth coordinated research meeting on the measurement and evaluation of transactinium isotope nuclear data, Vienna, 12-13 October 1981

    International Nuclear Information System (INIS)

    Lorenz, A.

    1981-12-01

    Proceedings of the fourth meeting of the participants in the IAEA Coordinated Research Programme to measure and evaluate the required nuclear decay data of heavy element radionuclides, convened by the IAEA Nuclear Data Section on 12-13 October 1981, at IAEA Headquarters in Vienna. The meeting participants reviewed the data requirements, updated and extended the recommended list of half-lives, and continued to review the status of alpha and gamma radiation spectra emitted in the decay of transactinium isotopes. (author)

  2. Summary Record of the Twenty-Sixth Meeting of the Working Party on International Nuclear Data Evaluation Co-operation

    International Nuclear Information System (INIS)

    Dupont, Emmeric

    2014-01-01

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countries) and CENDL (China) in close co-operation with the Nuclear Data Section of the International Atomic Energy Agency (IAEA). The working party was established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, validation, and related topics, and to provide a framework for co-operative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint evaluation and/or measurement efforts. This document is the executive summary of WPEC's 26. meeting held in 2014. It presents a brief review of the 2 days meeting in particular the Reports on experimental activities in Europe, Japan, USA and China, the Brief progress reports from the evaluation projects (ENDF, JEFF, JENDL, ROSFOND, CENDL, IAEA, TENDL) with the discussion of future plans, the Review of final or near-final subgroup reports, the Status of ongoing subgroups, the Proposals for new subgroups and some information about Conferences and meetings of interest to the nuclear data community. A list of participants and a list of reports presented at this meeting are attached in appendix

  3. Radionuclide decay data-evaluation and dissemination

    International Nuclear Information System (INIS)

    Helmer, R.G.

    1994-01-01

    There are many applications of nuclear chemistry and physics, as the variety of contents of this symposium demonstrate. Many of these applications require a knowledge of data on the decay of radionuclides, e.g., half-lives and radiation energies and emission probabilities. For over 50 years, people have been compiling and evaluating the measured data to obtain recommended values of these quantities. This has resulted in numerous sets of recommended values, many of which still have scientific, historical, or national reasons for existing. This history provides a background to the current situation which involves the coexistence of the Table of Radioactive isotopes, the ENSDF file and the Nuclear Data Sheets, the Table de Radionucleides, IAEA Coordinated Research Program results, the ENDF/B-VI decay data file, etc. Visions of the future include new styles of evaluations and feedback from interested users

  4. Current status of nuclear decay data and report on the IAEA Coordinated Research Programme on the measurement and evaluation of transactinium isotope nuclear decay data

    International Nuclear Information System (INIS)

    Reich, C.W.; Vaninbroukx, R.

    1984-01-01

    In 1977, the IAEA organized a Coordinated Research Programme to address the needs for highly accurate actinide-nuclide decay data identified at the first Advisory Group Meeting on Transactinium Isotope Nuclear Data, held in Karlsruhe in 1975. During the years of its existence, this CRP has made significant strides towards achieving the goals outlined at Karlsruhe and subsequently refined at a second Advisory Group Meeting, held in Cadarache in 1979. In this paper, the make-up of the CRP and its work in the areas of decay-data measurement and evaluation are presented and its significant accomplishments summarized. We also discuss the contents and philosophy of the final report, containing the results of the measurements and evaluations carried out by the CRP participants, to be published following the planned termination of this Programme in November, 1984. 82 references

  5. Fifth research coordination meeting on the measurement and evaluation of transactinium isotope nuclear data. Central Bureau for Nuclear Measurements, Geel, Belgium, 1-3 September 1982

    International Nuclear Information System (INIS)

    Lorenz, A.

    1982-12-01

    Proceedings of the fifth meeting of the participants in the IAEA Coordinated Research Programme to measure and evaluate the required nuclear decay data of heavy element radionuclides, convened by the IAEA Nuclear Data Section on 1-3 September 1982 at CBNM, Geel, Belgium. The meeting participants reviewed the data requirements, updated and extended the recommended list of half-lives, and continued to review the status of alpha and gamma radiation spectra emitted in the decay of transactinium isotopes. (author)

  6. 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.

  7. The EFF Project Status and the NEA Nuclear Data Services

    International Nuclear Information System (INIS)

    Henriksson, H.; Kodeli, I.; Nordborg, C.; Forrest, R.; Batistoni, P.; Fischer, U.

    2006-01-01

    The OECD Nuclear Energy Agency (NEA) Data Bank is part of an international network of data centres in charge of the compilation and dissemination of basic nuclear data. Through its activities in the reaction data field, the NEA participates in the production of data and their distribution to its users. The NEA Data Bank administrates the collection and validation as well as the distribution of the Joint Evaluated Fusion and Fission (JEFF) library. The JEFF project has evolved from two separate projects, namely the European Fusion File (EFF) and the Joint Evaluated File (JEF), to JEFF with the latest release of the library, JEFF-3.1, in May 2005. The EFF Project is a collaborative project with work funded by the European Fusion Development Agreement (EFDA). The tasks within the project comprise new data evaluation and verification of activation and transport data, calculation methods and validation via integral experiments. The EFF project brings together all available expertise in Europe, relating to the nuclear data requirements of existing and future fusion devices. EFF contributed greatly to the successful release of the internationally recognised nuclear data library JEFF-3.1. The NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC) is established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations and validation. WPEC provides a framework for co-operative activities between the participating projects, such as the high priority request list that is a collection of experimental data requests of special interest in a certain project, such as JEFF or ITER. The NEA provides also computer program services for nuclear energy and radiation physics applications. Of special interest for fusion applications are the integral experiments, such as SINBAD, with radiation shielding and dosimetry experiments including many fusion neutronics shielding experiments. (author)

  8. Compilation of requests for nuclear data

    International Nuclear Information System (INIS)

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

    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

  9. A code guidance system for integrated nuclear data evaluation system on the basis of knowledge engineering technology

    International Nuclear Information System (INIS)

    Fukahori, Tokio; Nakagawa, Tsuneo

    1994-01-01

    The integrated nuclear data evaluation system (INDES) is being made in order to support the nuclear data evaluation work. A guidance system in INDES, 'Evaluation Tutor (ET)', is under development in order to support users in selecting the most suitable set of theoretical calculation codes by applying knowledge engineering technology and the experiences of evaluation work for JENDL-3. In this paper, the function of ET is introduced as well as the functions and databases of INDES. An example run of ET for 56 Fe in the 1-20 MeV neutron energy region is also explained. (author)

  10. 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.

  11. Fast probabilistic file fingerprinting for big data.

    Science.gov (United States)

    Tretyakov, Konstantin; Laur, Sven; Smant, Geert; Vilo, Jaak; Prins, Pjotr

    2013-01-01

    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 concerns logistics within and between data centers, but is also important for workstation users in the analysis phase. Common usage patterns, such as comparing and transferring files, are proving computationally expensive and are tying down shared resources. We present an efficient method for calculating file uniqueness for large scientific data files, that takes less computational effort than existing techniques. This method, called Probabilistic Fast File Fingerprinting (PFFF), exploits the variation present in biological data and computes file fingerprints by sampling randomly from the file instead of reading it in full. Consequently, it has a flat performance characteristic, correlated with data variation rather than file size. We demonstrate that probabilistic fingerprinting can be as reliable as existing hashing techniques, with provably negligible risk of collisions. We measure the performance of the algorithm on a number of data storage and access technologies, identifying its strengths as well as limitations. Probabilistic fingerprinting may significantly reduce the use of computational resources when comparing very large files. Utilisation of probabilistic fingerprinting techniques can increase the speed of common file-related workflows, both in the data center and for workbench analysis. The implementation of the algorithm is available as an open-source tool named pfff, as a command-line tool as well as a C library. The tool can be downloaded from http://biit.cs.ut.ee/pfff.

  12. 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)

  13. ENDF-6 File 30: Data covariances obtained from parameter covariances and sensitivities

    International Nuclear Information System (INIS)

    Muir, D.W.

    1989-01-01

    File 30 is provided as a means of describing the covariances of tabulated cross sections, multiplicities, and energy-angle distributions that result from propagating the covariances of a set of underlying parameters (for example, the input parameters of a nuclear-model code), using an evaluator-supplied set of parameter covariances and sensitivities. Whenever nuclear data are evaluated primarily through the application of nuclear models, the covariances of the resulting data can be described very adequately, and compactly, by specifying the covariance matrix for the underlying nuclear parameters, along with a set of sensitivity coefficients giving the rate of change of each nuclear datum of interest with respect to each of the model parameters. Although motivated primarily by these applications of nuclear theory, use of File 30 is not restricted to any one particular evaluation methodology. It can be used to describe data covariances of any origin, so long as they can be formally separated into a set of parameters with specified covariances and a set of data sensitivities

  14. Research on technology of evaluating thermal property data of nuclear power materials

    International Nuclear Information System (INIS)

    Imai, Hidetaka; Baba, Tetsuya; Matsumoto, Tsuyoshi; Kishimoto, Isao; Taketoshi, Naoyuki; Arai, Teruo

    1997-01-01

    For the materials of first wall and diverter of nuclear fusion reactor, in order to withstand steady and unsteady high heat flux load, excellent thermal characteristics are required. It is strongly demanded to measure such thermal property values as heat conductivity, heat diffusivity, specific heat capacity, emissivity and so using small test pieces up to higher than 2000degC. As the materials of nuclear reactors are subjected to neutron irradiation, in order to secure the long term reliability of the materials, it is very important to establish the techniques for forecasting the change of the thermal property values due to irradiation effect. Also the establishment of the techniques for estimating the thermal property values of new materials like low radioactivation material is important. In National Research Laboratory of Metrology, the research on the advancement of the measuring technology for high temperature thermal properties has resulted in the considerably successful development of such technologies. In this research, the rapid measurement of thermal property values up to superhigh temperature with highest accuracy, the making of thermal property data set of high level, the analysis and evaluation of the correlation of material characters and thermal property values, and the development of the basic techniques for estimating the thermal property values of solid materials are aimed at and advanced. These are explained. (K.I.)

  15. NJOY. A comprehensive system for the processing of ENDF formatted nuclear data

    International Nuclear Information System (INIS)

    Muir, D.W.

    1990-07-01

    An introduction to the program system NJOY is given which processes data files of evaluated neutron nuclear data coded in ENDF format. NJOY is primarily used for neutron and photon transport calculations for nuclear power reactor design. The NJOY code is not available from the IAEA Nuclear Data Section but may be obtained from the Reactor Shielding Information Center, Oak Ridge, USA. (author). 10 refs, 1 fig

  16. Nuclear Data in Argentina (1992 -1993)

    International Nuclear Information System (INIS)

    Ricabarra, G. H.

    1993-03-01

    A progress report of nuclear data research in Argentina is given for the years 1992/1993, including the WIMS nuclear data library update project, and measurements and evaluations of selected neutron induced nuclear reactions. (author)

  17. 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 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.

  18. Co-ordinated Evaluation of Plutonium-239 in the Resonance Region - A report by the Working Party on International Nuclear Data Evaluation Co-operation of the NEA Nuclear Science Committee

    International Nuclear Information System (INIS)

    De Saint Jean, Cyrille; Noguere, Gilles; Peneliau, Yannick; Bernard, David; Serot, Olivier; McKnight, Richard D.; Leal, Luiz Carlos; Derrien, Herve; Kahler, Albert C.

    2014-04-01

    The Working Party on International Nuclear Data Evaluation Co-operation (WPEC) has been established under the aegis of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data evaluations, validation and related topics. Its aim is also to provide a framework for co-operative activities between the members of the major nuclear data evaluation projects. This includes the possible exchange of scientists in order to encourage co-operation. Requirements for experimental data resulting from this activity are compiled. The WPEC determines common criteria for evaluated nuclear data files with a view to assessing and improving the quality and completeness of evaluated data. The parties to the project are: BROND (Russian Federation), ENDF (United States), JENDL (Japan) and JEFF (other NEA Data Bank member countries), as well as CENDL (China) in close co-operation with the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report has been issued by the WPEC Subgroup 34 with a view to solving a general discrepancy when calculating criticality benchmarks with plutonium, using the most recent evaluated data libraries. This international effort enabled the delivery of a single set of resonance parameters up to 2.5 keV. The large fluctuations of the prompt neutron multiplicities were correctly reproduced with a phenomenological decomposition of the multiplicity that involved the two-step (n,γf) process. Performances of the new 239 Pu evaluation were tested over a broad set of integral data (ICSBEP, mock-up experiments performed in the CEA facilities and in power reactors). An overall good agreement was achieved between the calculations and the experimental results. The international effort performed in the framework of this Subgroup enabled delivery of a single set of resonance parameters up to 2.5 keV able to provide good C/E results over a broad set of integral data. The resonance analysis has been performed

  19. Nuclear energy data

    International Nuclear Information System (INIS)

    2002-01-01

    This new edition of Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of essential statistics on nuclear energy in OECD countries, offers additional textual and graphical information as compared with previous editions. It provides the reader with a comprehensive but easy-to-access overview on the status of and trends in the nuclear power and fuel cycle sector. This publication is an authoritative information source of interest to policy makers, experts and academics involved in the nuclear energy field. (authors)

  20. 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.

  1. Nuclear energy data

    International Nuclear Information System (INIS)

    2003-01-01

    This new edition of Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of essential statistics on nuclear energy in OECD countries, offers additional textual and graphical information as compared with previous editions. It provides the reader with a comprehensive but easy-to-access overview on the status of and trends in the nuclear power and fuel cycle sector. This publication is an authoritative information source of interest to policy makers, experts and academics involved in the nuclear energy field. (author)

  2. The US Nuclear Data Network

    International Nuclear Information System (INIS)

    1990-01-01

    This report contains: meeting of the Formats and Procedures Subcommittee of the USNDN; minutes of the Formats and Procedures Subcommittee meeting; University of Pennsylvania progress report since October 1989; TUNL A = 3 - 20 data project activity report 1990; Mass-chain evaluation and related activities at INEL; isotopes project report; nuclear data project activity report; the NNDC activity report; status of mass-chain evaluations; nuclear data sheets processing statistics for 1985--1990; nuclear data sheets update for A = 50; table of isotopes timetable; on-line access: status and service statistics; electronic nuclear data base environments; NNDC response on increase in productivity; a short ENSDF evaluation cycle; mass-chain evaluation and productivity; and response to panel report re: evaluation cycle time etc

  3. Twenty-eighth Meeting of the Working Party on International Nuclear Data Evaluation Co-operation. Summary Record

    International Nuclear Information System (INIS)

    Chadwick, Mark; ); Danon, Yaron; Herman, Mike; ); Dunn, Mike; ); Kahler, Albert Skip; ); Jacqmin, Robert; ); Plompen, Arjan; ); Fukahori, Tokio; ); Harada, Hideo; ); Iwamoto, Osamu; Yokoyama, Kenji; ); Grudzevich, Oleg; ); Ge, Zhigang; Ruan, Xichao; Wu, Haicheng; Koning, Arjan; ); Mills, Robert; ); Mcnabb, Dennis; ); Palmiotti, Giuseppe; ); Noguere, Gilles; ); Leal, Luiz; ); Cabellos, Oscar; )

    2016-01-01

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countries) and CENDL (China) in close co-operation with the Nuclear Data Section of the International Atomic Energy Agency (IAEA). The working party was established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, 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 evaluation and/or measurement efforts. The 28. Meeting of the WPEC was the occasion to review the experimental activities, the evaluation projects and the Status of subgroups. This document is the summary record of the meeting. It presents: 1 - The reports on experimental activities: Experimental nuclear data activities of relevance to the evaluation projects were reviewed. Detailed information about the experimental activities is given in the reports and view-graphs presented at the meeting. 2 - The review of final or near-final subgroup reports. Results and conclusions of completed or near-completed subgroups were discussed. A summary table of all subgroup status is given in Annex 3. 3 - The status of ongoing subgroups. Activities of ongoing subgroups were presented. A summary table of all subgroup status is given in Annex 3. 4 - The proposals for new subgroups. The subgroup proposal was reviewed by WPEC. Detailed information about this proposal is given in the document. 5 - The forthcoming meetings of interest. The documents presented at the twenty-eight WPEC meeting are presented in the annex 2: Annex 2.1 Working Party on International Nuclear Data Evaluation Co-operation - WPEC; Annex 2.2 WPEC Long-term mandate (updated and extended) on a 'Expert Group on the High Priority Request

  4. Online nuclear data service

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1994-01-01

    The US National Nuclear Data Center and the IAEA Nuclear Data Section offer online computer access through international networks to their nuclear-physics and photoatomic numeric databases, related bibliographic systems and other related information of interest to basic and applied research and technology. A detailed description of the access procedures, the technical requirements, and the available databases is given. (author)

  5. Online nuclear data service

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1994-01-01

    The US National Nuclear Data Center and the IAEA Nuclear Data Section offer online computer access through international networks to their nuclear-physics and photo-atomic numeric databases, related bibliographic systems and other related information of interest to basic and applied research and technology. A detailed description of the access procedures, the technical requirements, and the available databases is given. (author)

  6. Online Nuclear Data Service

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1994-01-01

    The US National Nuclear Data Center and the IAEA Nuclear Data Section offer online computer access through international networks to their nuclear-physics and photo-atomic numeric databases, related bibliographic systems and other related information of interest to basic and applied research and technology. A detailed description of the access procedures, the technical requirements, and the available databases is given. (author)

  7. Online nuclear data service

    International Nuclear Information System (INIS)

    Dunford, C.L.; Burrows, T.W.

    1998-01-01

    The US National Nuclear Data Center and the IAEA Nuclear Data Section offer online computer access through international networks to their nuclear-physics and photo-atomic numeric databases, related bibliographic systems and other related information of interest to basic and applied research and technology. A detailed description of the access procedures, the technical requirements, and the available databases is given. (author)

  8. Online nuclear data service

    Energy Technology Data Exchange (ETDEWEB)

    Dunford, C L [International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section; Burrows, T W [National Nuclear Data Center, Upton, NY (United States)

    1994-12-31

    The US National Nuclear Data Center and the IAEA Nuclear Data Section offer online computer access through international networks to their nuclear-physics and photo-atomic numeric databases, related bibliographic systems and other related information of interest to basic and applied research and technology. A detailed description of the access procedures, the technical requirements, and the available databases is given. (author).

  9. Evaluation of neutron and proton nuclear data of {sup 28}Si for energies up to 200 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Sun, Weili [Kyushu Univ., Department of Applied Quantum Physics and Nuclear Engineering, Fukuoka (Japan); Watanabe, Y. [Kyushu Univ., Department of Advanced Energy Engineering Science, Fukuoka (Japan); Sukhovitskii, E. Sh. [Radiation Physics and Chemistry Problems Institute, Minsk-Sosny (Belarus); Iwamoto, O.; Chiba, S. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    The neutron and proton nuclear data of {sup 28}Si up to 200 MeV are evaluated for various nuclear engineering applications. The soft rotator model and the coupled-channel method are used to perform a consistent analysis of the collective band structure of {sup 28}Si and nucleon scattering from {sup 28}Si. The GNASH nuclear model code is used for compound and preequilibrium particle emission calculations, where the emission of {sup 3}He is also included. Comparisons show overall good agreement with various experimental data. (author)

  10. Evaluation of neutron and proton nuclear data of 28Si for energies up to 200 MeV

    International Nuclear Information System (INIS)

    Sun, Weili; Watanabe, Y.; Sukhovitskii, E. Sh.; Iwamoto, O.; Chiba, S.

    2001-01-01

    The neutron and proton nuclear data of 28 Si up to 200 MeV are evaluated for various nuclear engineering applications. The soft rotator model and the coupled-channel method are used to perform a consistent analysis of the collective band structure of 28 Si and nucleon scattering from 28 Si. The GNASH nuclear model code is used for compound and preequilibrium particle emission calculations, where the emission of 3 He is also included. Comparisons show overall good agreement with various experimental data. (author)

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

    International Nuclear Information System (INIS)

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

    1988-11-01

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

  12. Nuclear Data Section status report

    International Nuclear Information System (INIS)

    Muir, D.; Pronyaev, V.G.

    2001-01-01

    This report summarises the Nuclear Structure and Decay Data (NSDD) related activity of the IAEA Nuclear Data Section (NDS) for the period October 1998 to September 2000. It covers both online NSDD user service either Telnet or Web services, and offline NSDD service. The NSDD development programs and projects are related to NDS contribution to the IAEA Analytical Quality Control Services program, Coordinated Research Project on nuclear model parameter testing for nuclear data evaluation, Coordinated Research Project on updating of x-ray and gamma-ray decay data standards for detector calibration, and Coordinated Research Project on development of database for prompt gamma-neutron activation analysis

  13. Maslov. Evaluated neutron reaction data for Am and Cm isotopes. Summary documentation

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1996-01-01

    The nuclear data file by V.M. Maslov et al includes evaluated neutron reaction data for Am-241,243 Cm-243-245,246 in EDNF-6 format. The data are available from the IAEA Nuclear Data Section, costfree upon request. (author)

  14. Measurement of leakage neutron spectra from silicon carbide cylinders with D–T neutrons and validation of evaluated nuclear data

    International Nuclear Information System (INIS)

    Luo, F.; Han, R.; Nie, Y.; Chen, Z.; Zhang, S.; Shi, F.; Lin, W.; Ren, P.; Tian, G.; Sun, Q.; Gou, B.; Ruan, X.; Ren, J.; Ye, M.

    2016-01-01

    Highlights: • Evaluated data for SiC are validated by a high precision benchmark experiment. • Leakage neutron spectra from SiC cylinders are measured at 60° and 120° using time-of-flight method. • The experimental results are compared with the MCNP-4C calculations with ENDF-BVII.1, JENDL-4.0 and CENDL-3.1 libraries. • The SiC evaluated nuclear data from CENDL-3.1 library was checked for the first time and proved to be reliable. - Abstract: Benchmarking of evaluated nuclear data libraries was performed for 14 MeV neutrons on silicon carbide samples. The experiments were carried out by using the benchmark experimental facility at China Institute of Atomic Energy (CIAE). The leakage neutron spectra from SiC (Φ13 cm × 20 cm) at 60° and 120° and SiC (Φ13 cm × 2 cm) at 60° were measured by the TOF method. The measured spectra are well reproduced by MCNP-4C calculations with the CENDL-3.1, ENDF/B-VII.1 and JENDL-4.0 evaluated nuclear data libraries, except 5–8 MeV range for 20 cm thickness. The discrepancies are mostly considered as caused by the improper evaluation of the angular distribution and secondary neutron energy distribution of the elastic scattering and inelastic scattering in evaluated nuclear data libraries.

  15. Measurement of leakage neutron spectra from silicon carbide cylinders with D–T neutrons and validation of evaluated nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Luo, F. [School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026 (China); Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Han, R. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing 102413 (China); Nie, Y. [Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing 102413 (China); Chen, Z., E-mail: zqchen@impcas.ac.cn [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Zhang, S. [College of Physics Electronic Information, Inner Mongolia University for the Nationalities, Tongliao 028000 (China); Shi, F.; Lin, W.; Ren, P.; Tian, G.; Sun, Q.; Gou, B. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Ruan, X.; Ren, J. [Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing 102413 (China); Ye, M. [School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026 (China)

    2016-11-15

    Highlights: • Evaluated data for SiC are validated by a high precision benchmark experiment. • Leakage neutron spectra from SiC cylinders are measured at 60° and 120° using time-of-flight method. • The experimental results are compared with the MCNP-4C calculations with ENDF-BVII.1, JENDL-4.0 and CENDL-3.1 libraries. • The SiC evaluated nuclear data from CENDL-3.1 library was checked for the first time and proved to be reliable. - Abstract: Benchmarking of evaluated nuclear data libraries was performed for 14 MeV neutrons on silicon carbide samples. The experiments were carried out by using the benchmark experimental facility at China Institute of Atomic Energy (CIAE). The leakage neutron spectra from SiC (Φ13 cm × 20 cm) at 60° and 120° and SiC (Φ13 cm × 2 cm) at 60° were measured by the TOF method. The measured spectra are well reproduced by MCNP-4C calculations with the CENDL-3.1, ENDF/B-VII.1 and JENDL-4.0 evaluated nuclear data libraries, except 5–8 MeV range for 20 cm thickness. The discrepancies are mostly considered as caused by the improper evaluation of the angular distribution and secondary neutron energy distribution of the elastic scattering and inelastic scattering in evaluated nuclear data libraries.

  16. Bonderenko self-shielded cross sections and multiband parameters derived from the LLL Evaluated-Nuclear-Data Library (ENDL)

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1978-01-01

    Bonderenko self-shielded cross sections and multiband parameters from the Lawrence Livermore Laboratory Evaluated-Nuclear-Data Library (ENDL) as of July 4, 1978 are presented. These data include total, elastic, capture, and fission cross sections in the TART 175 group structure. Multiband parameters are listed. Bonderenko self-shielded cross section and the multiband parameters are presented on microfiche

  17. 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.

  18. Handbook of nuclear data for safeguards

    International Nuclear Information System (INIS)

    Nichols, A.L.; Verpelli, M.; Aldama, D.L.

    2007-01-01

    A set of recommended nuclear data have been assembled that are judged to be suitable for application with respect to nuclear materials accounting techniques. These revised data supersede the tabulations to be found within IAEA report INDC(NDS)-376, December 1997. The update is based on available evaluated nuclear databases and recently published files, books and technical reports. Every effort has been made to ensure that the recommended data are credible and correct with respect to their original sources. Section A contains decay data, thermal neutron capture cross section data, resonance integrals and neutron emission yields per fission for relevant actinides and their natural decay products; Section B includes decay and thermal neutron capture cross section data for some important fission products; Section C presents fission product yield data for selected actinides. The recommended data sets can be inspected as tables in this INDC(NDS) report, or through the adoption and use of appropriate software. Users are referred to 'Interactive Chart of Nuclides' for an introduction to software that can be downloaded from the Web to undertake rapid inspections of the assembled database. The Web site is located at http://www-nds.iaea.org/sgnucdat/. (author)

  19. INDC/NEANDC nuclear standards file 1980 version

    International Nuclear Information System (INIS)

    1981-09-01

    This working document of the Nuclear Standards Subcommittee of the International Nuclear Data Committee (INDC) summarizes the status of nuclear standards as of the 11th INDC meeting (6/'80) with selective updating to approximately 5/'81. This version of the file is presented in two sections as per the following. The first section (A) consists of numerical tabulations of the respective quantities generally including quantitative definition of the uncertainties. Most of these numerical values are taken from the ENDF/B-V file which is available on a world-wide basis through the 4-Center network. Some guidelines as to appropriate usage are also given. The objective is the provision of a concise and readily used reference guide to essential standard-nuclear quantities useful for a diversity of basic and applied endeavors. The second section (B) briefly summarizes the contemporary status of each of the standards tabulated in Section A and additional items, including recent relevant work and areas of continuing uncertainty. These brief reviews were prepared under the auspices of the Committee by outstanding specialists in the respective fields. In many instances they are new statements but, where review indicates that the previous statement (see INDC-30/L+sp) remains appropriate, the previous summaries were retained; often with additional remarks by the editor

  20. Workshop on nuclear structure and decay data: Theory and evaluation, 2008

    International Nuclear Information System (INIS)

    Nichols, A.L.; McLaughlin, P.K.

    2008-06-01

    A two-week Workshop on Nuclear Structure and Decay Data under the auspices of the IAEA Nuclear Data Section was organised and held at the Abdus Salam International Centre for Theoretical Physics (ICTP) in Trieste, Italy from 28 April to 9 May 2008. This workshop constituted a further development of previous Nuclear Structure and Decay Data Workshops held in 2002, 2003, 2005 and 2006. The aims and contents of the 2008 workshop are summarized, along with the agenda, list of participants, comments and recommendations. All recent workshop material has been assembled in this INDC report, and is also freely available on CD-ROM (all relevant PowerPoint presentations and manuals along with appropriate computer codes). (author)

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

    Directory of Open Access Journals (Sweden)

    Park Tae-Sun

    2017-01-01

    Full Text Available 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.

  2. 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.

  3. Nuclear energy data

    International Nuclear Information System (INIS)

    2004-01-01

    This new edition of Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of essential statistics on nuclear energy in OECD countries, offers additional graphical information as compared with previous editions allowing a rapid comparison between capacity and requirements in the various phases of the nuclear fuel cycle. It provides the reader with a comprehensive but easy-to-access overview on the status of and trends in the nuclear power and fuel cycle sector. This publication is an authoritative information source of interest to policy makers, experts and academics involved in the nuclear energy field. (author)

  4. 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.

  5. 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...

  6. 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...

  7. Communication of nuclear data progress

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-15

    This is the 30th issue of Communication of Nuclear Data Progress (CNDP), in which the progress and achievements in nuclear data field in China during 2004 are carried. It includes the evaluations and model calculations of neutron data for n+{sup 31}P, {sup 59}Co, {sup 92-106}Mo, {sup Nat-116}Cd, {sup 233}U and the covariance data evaluation of experimental data for {sup 27}Al, update the decay data for radionuclide {sup 7}Be. Some results of studies for nuclear evaluation tool and model are also included in this issue, i.e. reaction mechanism studies of {sup 5}He, a new method of evaluating the discrepant data, linear fit of correlative data by least squared method et al. (authors)

  8. Communication of nuclear data progress

    International Nuclear Information System (INIS)

    2006-07-01

    This is the 30th issue of Communication of Nuclear Data Progress (CNDP), in which the progress and achievements in nuclear data field in China during 2004 are carried. It includes the evaluations and model calculations of neutron data for n+ 31 P, 59 Co, 92-106 Mo, Nat-116 Cd, 233 U and the covariance data evaluation of experimental data for 27 Al, update the decay data for radionuclide 7 Be. Some results of studies for nuclear evaluation tool and model are also included in this issue, i.e. reaction mechanism studies of 5 He, a new method of evaluating the discrepant data, linear fit of correlative data by least squared method et al. (authors)

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

    International Nuclear Information System (INIS)

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

    2010-01-01

    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 137 Cs, 131 I and 60 Co (R 2 = 0.55-0.73 and p 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 μBq 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.

  10. The Russian nuclear data research programme

    International Nuclear Information System (INIS)

    1995-11-01

    The report contains the Russian programme of nuclear data research, approved by the Russian Nuclear Data Committee on 16 December 1994. It gives surveys on nuclear data needs, on the structure of nuclear data activities, on experimental facilities for nuclear data measurements at five Russian institutes, on theoretical model work, nuclear data evaluation, and nuclear data testing. It describes four Russian nuclear data centers and their relations to the International Nuclear Data Centres Network, and their holdings of nuclear data libraries of Russian and international origin. A summary of nuclear data applications in energy and non-energy fields is given. An appendix contains a detail nuclear data research programme for the years 1995 - 2005. (author). 16 refs, 1 fig., 6 tabs

  11. 2007 Nuclear Data Review

    International Nuclear Information System (INIS)

    Holden, N.E.

    2008-01-01

    The results of a review and evaluation of neutron and non-neutron nuclear data published in the scientific literature are presented. The status of new chemical elements is examined. Data on revised values for the isotopic composition of the elements are reviewed and recommended values are presented. Half-lives of very long-lived nuclides are presented, including double beta decay, double electron capture, long-lived alpha decay and long-lived beta decay. Data from new measurements on the very heavy elements (trans-meitnerium elements) are discussed and tabulated. The first observation of the radioactive decay mode of the free neutron is discussed. New measurements that have expanded the neutron drip line for magnesium and aluminum are discussed. Data on recent neutron cross-section and resonance integral measurements are also discussed

  12. Meeting Nuclear Data Needs for Advanced Reactor Systems. A report by the Working Party on International Nuclear Data Evaluation Co-operation of the NEA Nuclear Science Committee - NEA-NSC-WPEC-DOC--2014-446

    International Nuclear Information System (INIS)

    Harada, H.; Shibata, K.; Nishio, K.; Plompen, A.; Hambsch, F.J.; Schillebeeckx, P.; ); Igashira, M.; Gunsing, F.; Ledoux, X.; Palmiotti, G.; Haight, R.; Ullmann, J.; Tovesson, F.; Nelson, R.; Herman, M.; Hoblit, S.; Pronyaev, V.; Cano-Ott, D.; Junghans, A.; Calviani, M.; ); Schmidt, K.H.; ); Otsuka, N.; ); Dupont, E.; )

    2014-01-01

    To meet the requirement of accurate nuclear data for developing advanced nuclear systems, pertinent efforts in the fields of experiments and evaluations are still required and indispensable. As described in Section 3, there are striking technical advancements in nuclear data measurement methods. For example, high-intensity-pulsed neutrons generated by spallation reaction at CERN in Europe, LANSCE in USA, and J-PARC in Japan are available to obtain high-precision neutron TOF data. Finer corrections of traditional techniques are also possible by using recent Monte Carlo simulation techniques or refining existing data reduction codes such as REFIT, SAMMY etc. New concept of detectors and innovative methods using inverse reactions have also been developed and applied for nuclear data measurements. By using these state-of-art techniques, further improvements of nuclear data accuracy are expected. It is understood that the experimental result is the best estimate of the value of the measurement, and that all components of uncertainty contribute to the total uncertainty. However, some systematic effects are sometimes unrecognised and not discussed in published papers. It should be noted that only the known systematic effects are corrected and took into account in the total uncertainty. Some recommendations of collaborative path forward to meet the needs were summarised in Section 4. In order to obtain accurate nuclear data, it is important to measure nuclear data precisely and identify the unrecognised systematic effects as much as possible. Double-check experiments are indispensable to verify the results. International collaborations are effective in guaranteeing the independence of experiments. In order to demonstrate the effectiveness of such collaboration, an appropriate framework should be established, where serious and detailed scientific discussions are possible

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

    International Nuclear Information System (INIS)

    Murarka, I.P.

    1976-08-01

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

  14. Nuclear Data Processing for Generation of Stainless Steel Cross-Sections Data

    International Nuclear Information System (INIS)

    Suwoto; Zuhair

    2007-01-01

    Stainless steel has been used as important material in nuclear reactor and also in non nuclear industries. Nuclear data processing for generation of composite mixture cross-sections from several nuclides have been made. Provided evaluated nuclear data file (ENDF) such as ENDF/B- VI.8, JEFF-3.1 and JENDL-3.3 files were employed. Raw nuclear data cross-sections on file ENDF should be prepared and processed before it used in calculation. Sequence of nuclear data processing for generation of mixture cross-sections data from several nuclides is started from LINEAR, RECENT, SIGMA1 and MIXER codes taken from PREPR02000 utility code. Nuclear data processing is started from linearization of nuclear cross-sections data by using LINEAR code and counting background contribution of resonance parameter (MF2) with RECENT code (0 K) at energy ranges from 10 -5 to 10 7 eV. Afterward, the neutron cross-sections data should be processed and broadened to desire temperature (300 K) by using SIGMA1 code. Consistency of each cross-sections which used in nuclear data processing is checked and verified using FIXUP code. The next step is to define the composite mixture density (gr/cm 3 ) of stainless steel SUS-310 and weight fraction of each nuclide composition prior used it in MIXER code. All of the stainless steel SUS-310 cross sections are condensed to 650 energy groups structure (TART-energy structure) by using GROUPIE code to evaluate, analysis and review it more easily. The total, elastic scattering, non-elastic scattering and capture cross- sections of stainless steel SUS-310 have been made of ENDF/B-VI.8, JEFF-3.1 and JENDL-3.3 files. The stainless steel cross-sections made of ENDF/B- VI.8 file was taken as reference during validation process. The validation result of total cross-sections for stainless steel SUS-310 is clearly observed that the differences of total cross-sections error in nuclear data processing is relatively low than 0.01%. (author)

  15. Report of the Working Group Specialist's meeting on methods and practices in the field of nuclear data covariance

    International Nuclear Information System (INIS)

    Peelle, R.W.

    1986-01-01

    This paper discusses the need for nuclear data covariance files in various fields. The particular fields discussed are: fission reactor core physics, fast reactor shielding, fission reactor fuel cycle, fission power reactor pressure vessel surveillance, delayed neutron parameters for fission, fusion reactor blanket and shielding and fusion reactor dosimetry. Also discussed are the availability of sensitivity and uncertainty analysis techniques to utilize evaluated covariance files, covariance file processing codes and methods for evaluating nuclear data covariance quantiti. Topics on international cooperation are also discussed

  16. Evaluated Data Projects at the NEA

    International Nuclear Information System (INIS)

    Henriksson, H.; Rugama, Y.

    2006-01-01

    The OECD Nuclear Energy Agency (NEA) Data Bank is part of an international network of data centres in charge of the compilation and dissemination of basic nuclear data. The NEA offers easy access to the main nuclear databases with bibliographical information, evaluated libraries, e.g. the Joint Evaluated Fission and Fusion (JEFF) library, and experimental data in the EXFOR database, comprising published neutron induced as well as charged particle induced nuclear reaction data. The NEA Working Party on international nuclear data Evaluation Co-operation (WPEC) is established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations and validation. WPEC provides a framework for co-operative activities between six major evaluation projects (BROND, CENDL, Endf, FENDL, JEFF and JENDL). The NEA Data Bank administrates the collection and validation as well as the distribution of the JEFF library. The latest version, JEFF-3.1, was released in May 2005 and it contains a neutron data library, a proton data library and thermal scattering law data. The special purpose library on activation data contains 774 nuclei with over 12600 neutron induced reactions. Included is also radioactive decay data, with 3852 isotopes, and spontaneous and neutron induced fission yield data. The full documentation of the library is being prepared for publication in 2006. Processed JEFF-3.1 data files in ACE format, mainly for reactor physics applications, have been prepared and were distributed in spring 2006 with documentation. The processed files have been validated for criticality calculations, as well as for radiation physics application. The detailed analysis of the validation results will be very useful for improving the accuracy of evaluated data libraries. The display program JANIS has been developed at the NEA, and the latest version (JANIS-2.21) was released in October 2005. JANIS is designed to facilitate the visualisation and

  17. A New Approach for Nuclear Data Covariance and Sensitivity Generation

    International Nuclear Information System (INIS)

    Leal, L.C.; Larson, N.M.; Derrien, H.; Kawano, T.; Chadwick, M.B.

    2005-01-01

    Covariance data are required to correctly assess uncertainties in design parameters in nuclear applications. The error estimation of calculated quantities relies on the nuclear data uncertainty information available in the basic nuclear data libraries, such as the U.S. Evaluated Nuclear Data File, ENDF/B. The uncertainty files in the ENDF/B library are obtained from the analysis of experimental data and are stored as variance and covariance data. The computer code SAMMY is used in the analysis of the experimental data in the resolved and unresolved resonance energy regions. The data fitting of cross sections is based on generalized least-squares formalism (Bayes' theory) together with the resonance formalism described by R-matrix theory. Two approaches are used in SAMMY for the generation of resonance-parameter covariance data. In the evaluation process SAMMY generates a set of resonance parameters that fit the data, and, in addition, it also provides the resonance-parameter covariances. For existing resonance-parameter evaluations where no resonance-parameter covariance data are available, the alternative is to use an approach called the 'retroactive' resonance-parameter covariance generation. In the high-energy region the methodology for generating covariance data consists of least-squares fitting and model parameter adjustment. The least-squares fitting method calculates covariances directly from experimental data. The parameter adjustment method employs a nuclear model calculation such as the optical model and the Hauser-Feshbach model, and estimates a covariance for the nuclear model parameters. In this paper we describe the application of the retroactive method and the parameter adjustment method to generate covariance data for the gadolinium isotopes

  18. 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

  19. Nuclear energy data 2007

    International Nuclear Information System (INIS)

    2007-01-01

    This new edition of Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of essential statistics on nuclear energy in OECD countries, offers projections lengthened to 2030 for the first time and information on the development of new centrifuge enrichment capacity in member countries. The compilation gives readers a comprehensive and easy-to-access overview of the current situation and expected trends in various sectors of the nuclear fuel cycle, providing authoritative information to policy makers, experts and academics working in the nuclear energy field

  20. The benchmark experiment on slab beryllium with D–T neutrons for validation of evaluated nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Nie, Y., E-mail: nieyb@ciae.ac.cn [Science and Technology on Nuclear Data Laboratory, China Institute of Atomic Energy, Beijing 102413 (China); Ren, J.; Ruan, X.; Bao, J. [Science and Technology on Nuclear Data Laboratory, China Institute of Atomic Energy, Beijing 102413 (China); Han, R. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Zhang, S. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Inner Mongolia University for the Nationalities, Inner Mongolia, Tongliao 028000 (China); Huang, H.; Li, X. [Science and Technology on Nuclear Data Laboratory, China Institute of Atomic Energy, Beijing 102413 (China); Ding, Y. [Science and Technology on Nuclear Data Laboratory, China Institute of Atomic Energy, Beijing 102413 (China); School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000 (China); Wu, H.; Liu, P.; Zhou, Z. [Science and Technology on Nuclear Data Laboratory, China Institute of Atomic Energy, Beijing 102413 (China)

    2016-04-15

    Highlights: • Evaluated data for beryllium are validated by a high precision benchmark experiment. • Leakage neutron spectra from pure beryllium slab are measured at 61° and 121° using time-of-flight method. • The experimental results are compared with the MCNP-4B calculations with the evaluated data from different libraries. - Abstract: Beryllium is the most favored neutron multiplier candidate for solid breeder blankets of future fusion power reactors. However, beryllium nuclear data are differently presented in modern nuclear data evaluations. In order to validate the evaluated nuclear data on beryllium, in the present study, a benchmark experiment has been performed at China Institution of Atomic Energy (CIAE). Neutron leakage spectra from pure beryllium slab samples were measured at 61° and 121° using time-of-flight method. The experimental results were compared with the calculated ones by MCNP-4B simulation, using the evaluated data of beryllium from the CENDL-3.1, ENDF/B-VII.1 and JENDL-4.0 libraries. From the comparison between the measured and the calculated spectra, it was found that the calculation results based on CENDL-3.1 caused overestimation in the energy range from about 3–12 MeV at 61°, while at 121°, all the libraries led to underestimation below 3 MeV.

  1. The benchmark experiment on slab beryllium with D–T neutrons for validation of evaluated nuclear data

    International Nuclear Information System (INIS)

    Nie, Y.; Ren, J.; Ruan, X.; Bao, J.; Han, R.; Zhang, S.; Huang, H.; Li, X.; Ding, Y.; Wu, H.; Liu, P.; Zhou, Z.

    2016-01-01

    Highlights: • Evaluated data for beryllium are validated by a high precision benchmark experiment. • Leakage neutron spectra from pure beryllium slab are measured at 61° and 121° using time-of-flight method. • The experimental results are compared with the MCNP-4B calculations with the evaluated data from different libraries. - Abstract: Beryllium is the most favored neutron multiplier candidate for solid breeder blankets of future fusion power reactors. However, beryllium nuclear data are differently presented in modern nuclear data evaluations. In order to validate the evaluated nuclear data on beryllium, in the present study, a benchmark experiment has been performed at China Institution of Atomic Energy (CIAE). Neutron leakage spectra from pure beryllium slab samples were measured at 61° and 121° using time-of-flight method. The experimental results were compared with the calculated ones by MCNP-4B simulation, using the evaluated data of beryllium from the CENDL-3.1, ENDF/B-VII.1 and JENDL-4.0 libraries. From the comparison between the measured and the calculated spectra, it was found that the calculation results based on CENDL-3.1 caused overestimation in the energy range from about 3–12 MeV at 61°, while at 121°, all the libraries led to underestimation below 3 MeV.

  2. Nuclear and chemical data

    Energy Technology Data Exchange (ETDEWEB)

    De Regge, P.

    1978-12-15

    The neutron fission yield and other nuclear and chemical data of interest to the nuclear applications of mass spectrometry (mainly in the field of burnup determination) are examined. The performance of those determinations and the achievable accuracy should match the needs of the users of the data produced. 3 figures, 2 tables. (RWR)

  3. Proceedings of the 2000 symposium on nuclear data

    Energy Technology Data Exchange (ETDEWEB)

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

  4. Nuclear data for radiation shielding

    International Nuclear Information System (INIS)

    Miyasaka, Shunichi; Takahashi, Hiroshi.

    1976-01-01

    The third shielding expert conference was convened in Paris in Oct. 1975 for exchanging informations about the sensitivity evaluation of nuclear data in shielding calculation and integral bench mark experiment. The requirements about nuclear data presented at present from the field of nuclear design do not reflect sufficiently the requirements of shielding design, therefore it was the object to gather the requirements about nuclear data from the field of shielding. The nuclides used for shielding are numerous, and the nuclear data on these isotopes are required. Some of them cannot be ignored as the source of secondary γ-ray or in view of the radioactivation of materials. The requirements for the nuclear data of neutrons in the field of shielding are those concerning the reaction cross sections producing secondary γ-ray, the reaction cross sections including the production of secondary neutrons, elastic scattering cross sections, and total cross sections. The topics in the Paris conference about neutron shielding data are described, such as the methodology of sensitivity evaluation, the standardization of group constant libraries, the bench mark experiment on iron and sodium, and the cross section of γ-ray production. In the shielding of nuclear fission reactors, the γ-ray production owing to nuclear fission reaction is also important. In (d, t) fusion reactors, high energy neutrons are generated, and high energy γ-ray is emitted through giant E1 resonance. (Kako, I.)

  5. Nuclear decay data for dosimetry calculation. Revised data of ICRP Publication 38

    International Nuclear Information System (INIS)

    Endo, Akira; Yamaguchi, Yasuhiro

    2005-02-01

    New nuclear decay data used for dose calculation have been compiled for 1034 radionuclides, which are significant in medical, environmental and occupational exposures. The decay data were assembled from decay data sets of the Evaluated Nuclear Structure Data File (ENSDF), the latest version as of 2003. Basic nuclear properties in the ENSDF that are particularly important for calculating energies and intensities of radiations were examined and updated by referring to UNBASE2003/AME2003, the database for nuclear and decay properties of nuclides. In addition, modification of incomplete ENSDF was done for their format errors, level schemes, normalization records, and so on. The energies and intensities of emitted radiations by the nuclear decay and the subsequent atomic process were computed from the ENSDF using the computer code EDISTR04. EDISTR04 is an enhanced version of EDISTR used for assembling ICRP Publication 38 (ICRP38), and incorporates updates of atomic data and computation methods for calculating atomic radiations and spontaneous fission radiations. Quality assurance of the compiled data has been made by comparisons with various experimental data and decay databases prepared from different computer codes and data libraries. A package of the data files, called DECDC2 (Nuclear DECay Data for Dosimetry Calculation, Version 2), will succeed ICRP38 that has been used extensively in dose calculation and will be utilized in various fields. (author)

  6. MONJU experimental data analysis and its feasibility evaluation to build up the standard data base for large FBR nuclear core design

    International Nuclear Information System (INIS)

    Sugino, K.; Iwai, T.

    2006-01-01

    MONJU experimental data analysis was performed by using the detailed calculation scheme for fast reactor cores developed in Japan. Subsequently, feasibility of the MONJU integral data was evaluated by the cross-section adjustment technique for the use of FBR nuclear core design. It is concluded that the MONJU integral data is quite valuable for building up the standard data base for large FBR nuclear core design. In addition, it is found that the application of the updated data base has a possibility to considerably improve the prediction accuracy of neutronic parameters for MONJU. (authors)

  7. 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

  8. 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

  9. Data bank for nuclear-physical studies in educational facilities

    International Nuclear Information System (INIS)

    Boboshin, I.N.; Varlamov, V.V.; Ishkhanov, B.S.; Kapitonov, I.M.; Lenskaya, N.A.; Surgutanov, V.V.; Khoronenko, A.A.; Chernyaev, A.P.

    1986-01-01

    Purposes and tasks of nuclear data Centers of the USSR Ministry of Education are discussed in short. Files of both bibliographic and factographic nuclear-physical data widely used with the Centres to provide the state organizations and scientists, first of all educational facilities, with nuclear data to increase effectiveness of fundamental and applied investigations and educational process are described

  10. Nuclear Data Newsletter. No. 17

    International Nuclear Information System (INIS)

    1992-09-01

    This issue of the Nuclear Data Newsletter dated September 1992, gives information on the following topics: Data indexes and bibliographies, IAEA Nuclear Data Information System-on-line access, nuclear data processing computer codes, new data libraries, multigroup nuclear data, selected new publication on nuclear data, the network of nuclear data service centers which are all related to the activity of the Nuclear Data Section (NDS) of the IAEA

  11. 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...

  12. U.K. nuclear data progress report

    International Nuclear Information System (INIS)

    Findlay, D.J.S.; Cookson, J.A.

    1984-06-01

    The report summarises nuclear data research in the United Kingdom between January and December 1984. The nuclear data presented includes contributions from government research laboratories and Universities, as well as from various collaborations. The section on nuclear data forum includes three individual papers (being processed separately), these are: the DIMPLE criticality experiments, the potential use of criticality benchmark experiments in nuclear data evaluation, and the use of benchmark experiments for the validation of nuclear data. (U.K.)

  13. Nuclear Energy Data 2013

    International Nuclear Information System (INIS)

    2013-01-01

    Nuclear Energy Data is the OECD Nuclear Energy Agency's annual compilation of statistics and country reports documenting the status of nuclear power in the OECD area. Information provided by member country governments includes statistics on installed generating capacity, total electricity produced by all sources and by nuclear power, nuclear energy policies and fuel cycle developments, as well as projected generating capacity and electricity production to 2035, where available. Total electricity generation at nuclear power plants and the share of electricity production from nuclear power plants declined in 2012 as a result of operational issues at some facilities and suspended operation at all but two reactors in Japan. Nuclear safety was further strengthened in 2012 following safety reviews prompted by the Fukushima Daiichi nuclear power plant accident. Governments committed to maintaining nuclear power in the energy mix pursued initiatives to increase nuclear generating capacity. In Turkey, plans were finalised for the construction of the first four reactors for commercial electricity production. Further details on these and other developments are provided in the publication's numerous tables, graphs and country reports. This publication contains 'Statlinks'. For each StatLink, the reader will find a URL which leads to the corresponding spreadsheet. These links work in the same way as an Internet link [fr

  14. Evaluations for the German nuclear data library KEDAK-3. Pt. 2

    International Nuclear Information System (INIS)

    Goel, B.; Weller, F.

    1977-03-01

    In this report evaluations for the fissile and fertile isotopes performed at this laboratory during years 1973 to 1976 are presented. In particular the evaluations of the data for 235 U, 238 U, 239 Pu, 240 Pu and 241 Pu are described. Results of a preliminary check of the evaluated data for a variety of critical assemblies are also given in this report. (orig.) [de

  15. Nuclear data and human society

    International Nuclear Information System (INIS)

    Fuketa, Toyojiro

    2002-01-01

    Necessity and significance of nuclear data activities are discussed with background of the world typical aspects at the end of the 20th century. We have to overcome the worldwide adverse wind to nuclear power production with a view to preserving global environment including natural resources and climate. The nuclear data activities should be promoted further to achieve more and more wide comprehension and integrity of evaluated nuclear databases. The comprehensive evaluated nuclear databases which link microscopic world to macroscopic world may be of use to link science and technology with perception of the public, and to link science and technology with the other fields of learning, hence of use to coordinate and integrate natural, human, and social sciences. (author)

  16. Nuclear data for science and technology: Centres for development

    International Nuclear Information System (INIS)

    Lemmel, H.

    1996-01-01

    The IAEA Nuclear Data Section operates a centre which maintains the world's most comprehensive collection of nuclear and atomic data libraries that are needed for nuclear and radiation technologies in Member States. This article reviews these services, and the particular role of developing countries in this global data network. The availability of various data files to scientists in all IAEA Member States and its sources are mentioned. More recently the world's major data libraries have also become accessible on-line through NDIS, the Nuclear Data Information System, via the Internet or World Wide Web. The availability of various data files to scientists in all IAEA Member States and its sources are mentioned. Examples of nuclear data categories, Nuclear data libraries, Special purpose libraries, Network of nuclear data center and Nuclear data handbooks are given

  17. Co-ordination of the international network of nuclear structure and decay data evaluators. Summary report of an IAEA advisory group meeting

    International Nuclear Information System (INIS)

    Pronyaev, V.G.

    1999-03-01

    The IAEA Nuclear Data Section convened the thirteenth meeting of the International Nuclear Structure and Decay Data Evaluators Network at the IAEA Headquarters, Vienna, 14-17 December 1998. The meeting was attended by 30 scientists from 10 Member States and 2 international organizations concerned with compilation, evaluation, and dissemination of nuclear structure and decay data. The present document contains a meeting summary, the conclusions and recommendations, the data center reports and proposals considered by the participants. (author)

  18. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators. Summary report of an IAEA Technical Meeting

    International Nuclear Information System (INIS)

    Nichols, A.L.; Tuli, J.K.

    2007-09-01

    The IAEA Nuclear Data Section convened the 17th meeting of the International Network of Nuclear Structure and Decay Data Evaluators in St. Petersburg, Russian Federation, 11-15 June 2007. This meeting was attended by 27 scientists from 13 Member States 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. (author)

  19. Co-ordination of the international network of nuclear structure and decay data evaluators. Summary report of an IAEA advisory group meeting

    Energy Technology Data Exchange (ETDEWEB)

    Pronyaev, V G

    2001-02-01

    The IAEA Nuclear Data Section convened the fourteenth meeting of the International Nuclear Structure and Decay Data Evaluators Network at IAEA Headquarters, Vienna, 4-7 December 2000. The meeting was attended by 22 scientists from 7 Member States and 1 international organization concerned with compilation, evaluation, and dissemination of nuclear structure and decay data. The present document contains a meeting summary, the recommendations, the data center reports and proposals considered by the participants. (author)

  20. Collection and treatment of reliability data for nuclear plants

    International Nuclear Information System (INIS)

    McHugh, B.

    1973-09-01

    This paper describes some of the results achieved with the Argus data bank at the Institution of Thermal Power Engineering at the Chalmers University of Technology. This data bank, or rather data collection system, has been established to cover nuclear activities the world over. The system comprises in essence a number of data files. The prime files are those containing the basic data on the various plants - plant size and type, country and NSSS supplier and an indication of plantstatus. Further files contain plant design data and parameters and all available information on construction as commissioning timetables. To cover the operation of plant two files have been established. One file, which is updated on a monthly basis, contains power production statistics. The other file contains failure data. In this file are recorded the time and duration of plant shutdown together with the primary reason (s) for this. (M.S.)

  1. Nuclear energy and astrophysics applications of ENDF/B-VII.1 evaluated nuclear library

    International Nuclear Information System (INIS)

    Pritychenko, B.

    2012-01-01

    Recently released ENDF/B-VII.1 evaluated nuclear library contains the most up-to-date evaluated neutron cross section and covariance data. These data provide new opportunities for nuclear science and astrophysics application development. The improvements in neutron cross section evaluations and more extensive utilization of covariance files, by the Cross Section Evaluation Working Group (CSEWG) collaboration, allowed users to produce neutron thermal cross sections, Westcott factors, resonance integrals, Maxwellian-averaged cross sections and astrophysical reaction rates, and provide additional insights on the currently available neutron-induced reaction data. Nuclear reaction calculations using the ENDF/B-VII.1 library and current computer technologies will be discussed and new results will be presented

  2. Evaluation of the Latest Generic Data for PSA Applications of Domestic Nuclear Plants

    International Nuclear Information System (INIS)

    Hwang, Seok Won; Oh, Ji Yong; Lee, Byung Sik

    2009-01-01

    Generic data of domestic PSAs have mostly referred to 'Advanced Light Water Reactor (ALWR) Utility Requirements Document (URD) 'issued by EPRI. Generally, current data of domestic PSA have been customized with the generic and plant specific data through Bayesian analysis. The generic reference has established by collecting US nuclear plant practices from mid 1980s to early 1990s. Over the decade, US plants had showed low performances and capabilities in operation. On the other hand, the current domestic nuclear plants shows world class performance in operation and maintenance compared with the corresponding US nuclear plants in URD. Therefore, it is necessary to apply proper generic sources which can represent the current domestic plant performances and status. In 2007, the latest generic source (NUREG/CR-6928) is published by US NRC, which deals with new types of failure modes and analysis methods. A fundamental improvement in NUREG/CR-6928 compared with previous data source is the distinction between standby and alternating/running component basic events, which shows different failure mechanisms. Significant differences were also noted running failure events occurred within and beyond the first hour for emergency diesel generators, cooling units, and pumps. This was done because the historical perspective on running failure rates indicated approximately a factor of 15 differences between the two failure rates for several component types. ALWR URD uses lognormal distribution in the estimation of failure rates. On the contrary, NUREG/CR-6928 uses beta and gamma distributions for demand and running failures, respectively. This work has proposed an approach to the application of NUREG/CR-6928 to current PSA practice by comparing it with URD data. Moreover, this attempt results in eliciting substantial insights of the establishment of the domestic generic database

  3. Nuclear Energy Data - 2014

    International Nuclear Information System (INIS)

    2014-01-01

    Nuclear Energy Data is the OECD Nuclear Energy Agency's annual compilation of statistics and country reports documenting the status of nuclear power in the OECD area. Information provided by member country governments includes statistics on installed generating capacity, total electricity produced by all sources and by nuclear power, nuclear energy policies and fuel cycle developments, as well as projected generating capacity and electricity production to 2035, where available. Total electricity generation at nuclear power plants and the share of electricity production from nuclear power plants remained steady in 2013 despite the progressive shutdown of all reactors in Japan leading up to September and the permanent closure of six reactors in the OECD area. Governments committed to maintaining nuclear power in the energy mix advanced plans for increasing nuclear generating capacity, and progress was made in the development of deep geological repositories for spent nuclear fuel, with Finland expected to have the first such facility in operation in the early 2020's. Further details on these and other developments are provided in the publication's numerous tables, graphs and country reports. This publication contains 'StatLinks'. For each StatLink, the reader will find a URL which leads to the corresponding spreadsheet. These links work in the same way as an Internet link. (authors)

  4. Nuclear Energy Data - 2016

    International Nuclear Information System (INIS)

    2016-01-01

    Nuclear Energy Data is the Nuclear Energy Agency's annual compilation of statistics and country reports documenting nuclear power status in NEA member countries and in the OECD area. Information provided by governments includes statistics on installed generating capacity, total electricity produced by all sources and by nuclear power, nuclear energy policies and fuel cycle developments, as well as projections of nuclear generating capacity and electricity production to 2035, where available. Total electricity generation at nuclear power plants and the share of electricity production from nuclear power plants increased slightly in 2015, by 0.2% and 0.1%, respectively. Two new units were connected to the grid in 2015, in Russia and Korea; two reactors returned to operation in Japan under the new regulatory regime; and seven reactors were officially shut down - five in Japan, one in Germany and one in the United Kingdom. Governments committed to having nuclear power in the energy mix advanced plans for developing or increasing nuclear generating capacity, with the preparation of new build projects progressing in Finland, Hungary, Turkey and the United Kingdom. Further details on these and other developments are provided in the publication's numerous tables, graphs and country reports. This publication contains 'Stat Links'. For each Stat Link, the reader will find a URL which leads to the corresponding spreadsheet. These links work in the same way as an Internet link. (authors)

  5. Nuclear data newsletter. No. 27

    International Nuclear Information System (INIS)

    1999-03-01

    This issue announces the online and offline news concerning nuclear data cross section libraries and data processing codes available from Nuclear Data Section (NDS) of IAEA. In includes announcements on development activities of IAEA in the field of nuclear data collections and relevant computer codes and lists selected reports and documents on nuclear data as well as cooperating nuclear data service centres

  6. Nuclear data newsletter. No. 26

    International Nuclear Information System (INIS)

    1998-10-01

    This issue announces the online and offline news concerning nuclear data cross section libraries and data processing codes available from Nuclear Data Section (NDS) of IAEA. In includes announcements on development activities of IAEA in the field of nuclear data collections and relevant computer codes and lists selected reports and documents on nuclear data as well as cooperating nuclear data service centres

  7. Nuclear data newsletter. No. 29

    International Nuclear Information System (INIS)

    2000-04-01

    This issue announces the online and offline news concerning nuclear data cross section libraries and data processing codes available from Nuclear Data Section (NDS) of IAEA. In includes announcements on development activities of IAEA in the field of nuclear data collections and relevant computer codes and lists selected reports and documents on nuclear data as well as cooperating nuclear data service centres

  8. Nuclear data newsletter. No. 32

    International Nuclear Information System (INIS)

    2001-09-01

    This issue announces the online and offline news concerning nuclear data cross section libraries and data processing codes available from Nuclear Data Section (NDS) of IAEA. It includes announcements on development activities of IAEA in the field of nuclear data collections and relevant computer codes and lists selected reports and documents on nuclear data as well as cooperating nuclear data service centres

  9. Nuclear data newsletter. No. 28

    International Nuclear Information System (INIS)

    1999-10-01

    This issue announces the online and offline news concerning nuclear data cross section libraries and data processing codes available from Nuclear Data Section (NDS) of IAEA. In includes announcements on development activities of IAEA in the field of nuclear data collections and relevant computer codes and lists selected reports and documents on nuclear data as well as cooperating nuclear data service centres

  10. Nuclear astrophysics data at ORNL

    International Nuclear Information System (INIS)

    Smith, M.S.; Blackmon, J.C.

    1998-01-01

    There is a new program of evaluation and dissemination of nuclear data of critical importance for nuclear astrophysics within the Physics Division of Oak Ridge National Laboratory. Recent activities include determining the rates of the important 14 O(α,p) 17 F and 17 F(p,γ) 18 Ne reactions, disseminating the Caughlan and Fowler reaction rate compilation on the World Wide Web, and evaluating the 17 O(p,α) 14 N reaction rate. These projects, which are closely coupled to current ORNL nuclear astrophysics research, are briefly discussed along with future plans

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    1996-01-01

    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

  13. 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.

  14. Evaluation of 38 years of radiological environmental data for the nuclear research facility in South Africa

    Energy Technology Data Exchange (ETDEWEB)

    Cawood, Louise [Environmental Engineering Group, Department of Chemical Engineering, University of Pretoria (South Africa); Friend, Francois [Environmental Engineering Group, Department of Chemical Engineering, University of Pretoria (South Africa)]. E-mail: ffriend@eng.up.ac.za

    2005-07-01

    Environmental monitoring has been conducted at the South African National Nuclear Research Facility (Necsa site) for the past 38 years. Included in this monitoring programme was the assessment of water, fish and sediment samples. The objective of this project was to review the data of these assessments to establish if the Necsa activities had any impact on the environment. An assessment of the management of discharge limits was included in the review. Fluctuations in the data reviewed can partly be ascribed to errors in sampling techniques and analysis methods, but mostly to external factors. Two main external factors identified during the review were:*dilution effects based on the flowrate in the Crocodile River and the percentage of full capacity of the Hartbeespoort Dam, and*the atmospheric fallout from nuclear weapons testing.In this project, the impact of these factors were investigated with the help of correlation coefficient calculations and graphs. It was concluded that the flowrate of the Crocodile River and percentage full capacity of the Hartbeespoort Dam did have an impact on the beta activity measured in water and fish samples, and the {sup nat}U activities measured in water samples. The measured fallout from nuclear weapons testing in the southern hemisphere also had an impact on the beta activity in water.The assessment of the environmental monitoring data also showed that accidental releases were measurable in the environment. The added routine impact to a member of the public downstream from Necsa was on average an annual dose of 0.54{mu}Sv more than that to a person living upstream from Necsa, which is considered insignificant in international radiation protection norms. The conclusion can be made that the monitoring programme is successful in satisfying its main objective, which is to determine the effects of the discharges on the environment and the immediate population.

  15. Evaluation of WIMS-D/4 nuclear data library used on TRIGA reactor calculation

    International Nuclear Information System (INIS)

    Chen Wei; Xie Zhongsheng; Jiang Xinbiao; Chen Da

    1997-01-01

    The 69 groups constants of H in ZrH, 166 Er and 167 Er generated by NJOY and GASKET codes are inserted into WIMS nuclear data library WIMS-CNDC and WIMS-NINT libraries used on RTIGA reactor calculation are obtained. In order to check WIMS-CNDC and WIMS-NINT libraries, the scattering cross-section is compared with that in WIMS-IJS library. The group constant, K ∞ and temperature coefficient are calculated by using WIMS-CNDC, WIMS-NINT and WIMS-IJS. The results show the both libraries are suitable for calculation of TRIGA reactor

  16. Communication of nuclear data progress

    International Nuclear Information System (INIS)

    2001-01-01

    This is the 26th issue of Communication of Nuclear Data Progress (CNDP), in which the progress and achievements in nuclear data field from the last year up to now in China are carried. It includes the measurements of 71 Ga, 94 Zn, 191 Ir, 174 Hf(n, γ) and 114 Cd(n, 2n) cross sections, fission product yields of n + 235,238 U, DPA cross section calculated with UNF code, fission barrier parameter evaluation of some nuclides, production and transmission of covariance in the evaluation processing of fission yield data and transition analysis of Ne-like Ge XXIII

  17. Prospective economical study of the nuclear power file

    International Nuclear Information System (INIS)

    Charpin, J.M.; Dessus, B.; Pellat, R.

    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 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 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), cost overruns

  18. Parallel file system performances in fusion data storage

    International Nuclear Information System (INIS)

    Iannone, F.; Podda, S.; Bracco, G.; Manduchi, G.; Maslennikov, A.; Migliori, S.; Wolkersdorfer, K.

    2012-01-01

    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.

  19. 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.

  20. Nuclear data newsletter. No. 21

    International Nuclear Information System (INIS)

    1995-07-01

    This issue of the Nuclear Data Newsletter dated July 1995 gives information on the following topics: data indexes and bibliographies, information about how access to NDIS could be done, new nuclear data libraries received including package of nine data libraries on neutron reactions, a list of selected reports and documents on nuclear data, a data base on Nuclear Data Standards for Nuclear Measurements. Conference announcements and addresses of the co-operating nuclear data service centers are included