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)

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

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)

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

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

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.)

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)

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)

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).

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

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)

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)

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

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

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

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.

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.

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

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

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)

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

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

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)

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).

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)

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).

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.

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)

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)

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)

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

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

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)

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

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

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)

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

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)

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)

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)

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).

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.)

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

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)

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

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.)

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.)

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

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)

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)

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)

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.

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

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

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.

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.

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

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.

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.

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)

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)

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)

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)

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)

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

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.

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

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.

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)

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)

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)

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)

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)

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)

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.)

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

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.

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.

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.)

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

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.

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)

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

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.)

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)

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

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

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

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.)

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)

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.)

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)

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.

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)

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)

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

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)

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)

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)

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)

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

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)

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)

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)

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)

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

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.

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)

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)

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)

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

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

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

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)

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

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.

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

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)

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.

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.)

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

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)

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.

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)

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

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

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)

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)

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

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

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.

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.

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).

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

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

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

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.

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)

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.

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)

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

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)

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

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

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

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)

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)

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 ...

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.

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.

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

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.

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)

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)

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

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

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

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

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

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.)

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

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

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

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

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

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).

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)

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

Energy Technology Data Exchange (ETDEWEB)

Fukahori, Tokio [ed.

1998-11-01

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

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

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

Present status and history of nuclear data development for transmutation technology

CERN Document Server

Hasegawa, A

2002-01-01

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

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)

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

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

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

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)

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

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

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

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)

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

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

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

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

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)

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

The U.S. Nuclear Data Network: Summary of the twentieth meeting

International Nuclear Information System (INIS)

1994-01-01

Topics discussed at this meeting were: assessment of the nuclear data program from the perspective of the funding agency; status of high spin evaluations for ENSDF; recommendation for name change of master file from Nuclear Structure Reference to Nuclear Science Reference; status of ENSDF, Table of Isotopes, VuENSDF, on-line system at the NNDC, and Nuclear Data Sheets; summary of the discussion of the Formats and Procedures Subcommittee; long range plan for nuclear structure data; a description of methods of optimization of nuclear structure evaluations and how to evolve this activity into the forefront of research such as high-spin physics; code development which includes improvements in the databases and evaluator tools; and future means of data dissemination

TUNL Contributions in the US Nuclear Data Program and NSDD

Energy Technology Data Exchange (ETDEWEB)

Kelley, J. H.; Purcell, Jim; Sheu, G. [Triangle Universities Nuclear Laboratory, North Carolina (United States)

2013-08-15

Full text: Responsibilities: We are responsible for nuclear structure evaluation in the A=2-20 mass region - Energy Levels of Light Nuclei reviews published in Nuclear Physics A - ENSDF files for A=2-20 - XUNDL from A=2-20 - Web interface for A=3-20 Information Recent evaluation activities: - Published 'Energy Levels of Light Nuclei A=11' - Added A=11 ENSDF data set - Updated 7 b-n data sets (more to come) - Other work in progress: - A=12 Evaluation for 'Energy Levels' (Kelley) - A=13 Evaluation for 'Energy Levels' (Purcell) - Preparing A=12 ENSDF file Recent compilation activities for A=2-20: - Committed to XUNDL (A=3-20), 63 data sets 2012 (5-6/month) - Compilation of ground state decay and {beta}-decay references and data - Compilation of (p,X) and ({alpha},X) excitation functions - TUNL Dissertations, - http://www.tunl.duke.edu/{approx}gsheu/Theses/TUNL{sub T}heses.shtml. (author)

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.)

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)

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

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

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.)

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)

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

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

Science.gov (United States)

Kellett, Mark A.; Bersillon, Olivier

2017-09-01

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

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

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)

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

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)

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

The Nuclear CD-Rom

International Nuclear Information System (INIS)

James, J.Z.

1993-01-01

September 1992 will see the publication of the first open-quotes Nuclear CD-ROMclose quotes-a Compact Disk Read-Only Memory (CD-ROM) containing both the entire Evaluated Nuclear Data Files (ENDF) library and the Evaluated Nuclear Structure Data Files (ENSDF) library. The CD-ROM will also contain codes for processing and visualizing the data, and some nuclear physics codes to use the ENDF data. Finally, the data and program files will be accompanied by fully-formatted documentation that can be read on many different workstations and microcomputers

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

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

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

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

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.)

Index of nuclear data libraries available from the IAEA nuclear data section

International Nuclear Information System (INIS)

Lemmel, H.D.

1996-11-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, or online through www or INTERNET: either menu driven within the Nuclear Data Information System (NDIS), or through FTP file transfer. (author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1996-01-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, or online through the INTERNET computer network: either menu driven within the Nuclear Data Information System (NDIS), or through FTP file transfer. (author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.; Schwerer, O.

1997-01-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, CD-ROM or online through WWW, Telnet (menu driven within the Nuclear Data Information System NDIS), or through FTP file transfer. (author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1994-01-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, or online through the INTERNET computer network: either menu driven within the Nuclear Data Information System (NDIS), or through FTP file transfer. (author)

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

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

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

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

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)

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)

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.

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

Status of the JENDL activation file

International Nuclear Information System (INIS)

Nakajima, Yutaka

1996-01-01

The preliminary JENDL activation file was accomplished in February 1995 and has been used in the Japanese Nuclear Data Committee and as one of the data sources for the Fusion Evaluated Nuclear Data Library in IAEA. Since there are already big activation libraries in western Europe and United States, we are aiming at more accurate evaluation of important reactions to application to nuclear energy development rather than aiming at as many reaction data as in these big libraries. In the preliminary file 1,158 reaction cross sections have been compiled for 225 nuclides up to 20 MeV. (author)

The EFF project status and the NEA nuclear data services

Energy Technology Data Exchange (ETDEWEB)

Henriksson, H. [OECD Nuclear Energy Agency, 12 Blvd des Iles, 92130 Issy-les-Moulineaux (France)], E-mail: henriksson@nea.fr; Batistoni, P. [Associazione Euratom-ENEA sulla Fusione, Via E. Fermi 45, 00044 Frascati (Italy); Fischer, U. [Association FZK-Euratom, Postfach 3640, 76021 Karlsruhe (Germany); Forrest, R. [Euratom/UKAEA Fusion Association, Culham Science Centre, Oxfordshire OX14 3DB (United Kingdom); Kodeli, I.; Nordborg, C. [OECD Nuclear Energy Agency, 12 Blvd des Iles, 92130 Issy-les-Moulineaux (France)

2007-10-15

The OECD Nuclear Energy Agency (NEA) Data Bank participates in the production of data and their distribution to users including the collection and validation as well as the distribution of the Joint Evaluated Fission and Fusion (JEFF) library. The JEFF project has evolved from two separate projects, namely the European Fusion File (EFF) and the Joint Evaluated File (JEF), with the release of JEFF-3.1, in May 2005. The NEA also provides tools for the EFF project, such as computer codes for nuclear energy and radiation physics applications. Of special interest for fusion applications are the integral experiments collected in the SINBAD database, with radiation shielding and dosimetry experiments including many fusion neutronics shielding experiments. In this paper an overview will be given of the NEA, and some examples of nuclear data services offered, such as the SINBAD database. JANIS, a display program evaluated and experimental data developed at the NEA will be mentioned briefly. The main emphasis will be given to the EFF project including the contents of the new JEFF-3.1 library, released in May 2005. Examples of recent work are given as well as a discussion on the forth-coming evaluation efforts among the EFF collaborators.

The EFF project status and the NEA nuclear data services

International Nuclear Information System (INIS)

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

2007-01-01

The OECD Nuclear Energy Agency (NEA) Data Bank participates in the production of data and their distribution to users including the collection and validation as well as the distribution of the Joint Evaluated Fission and Fusion (JEFF) library. The JEFF project has evolved from two separate projects, namely the European Fusion File (EFF) and the Joint Evaluated File (JEF), with the release of JEFF-3.1, in May 2005. The NEA also provides tools for the EFF project, such as computer codes for nuclear energy and radiation physics applications. Of special interest for fusion applications are the integral experiments collected in the SINBAD database, with radiation shielding and dosimetry experiments including many fusion neutronics shielding experiments. In this paper an overview will be given of the NEA, and some examples of nuclear data services offered, such as the SINBAD database. JANIS, a display program evaluated and experimental data developed at the NEA will be mentioned briefly. The main emphasis will be given to the EFF project including the contents of the new JEFF-3.1 library, released in May 2005. Examples of recent work are given as well as a discussion on the forth-coming evaluation efforts among the EFF collaborators

RRDF-98. Russian reactor dosimetry file. Summary documentation

International Nuclear Information System (INIS)

Pashchenko, A.B.

1999-01-01

This document summarizes the contents and documentation of the new version of tile Russian Reactor Dosimetry File (RRDF-98) released in December 1998 by the Russian Center on Nuclear Data (CJD) at the Institute of Physics and Power Engineering, Russian Federation. This file contains the original evaluations of cross section data and covariance matrixes for 22 reactions which are used for neutron flux dosimetry by foil activation. The majority of the evaluations included in previous versions of the Russian Reactor Dosimetry Files (BOSPOR-80, RRGF-94 and RRDF-96) have been superseded by new evaluations. The evaluated cross sections of RRDF-98 averaged over 252-Cf and 235-U fission spectra are compared with relevant integral data. The data file is available from the IAEA Nuclear Data Section on diskette, cost free. (author)

Processing covariance data for the resonance region - International Evaluation Co-operation, V. 20

International Nuclear Information System (INIS)

Dunn, M.; Leal, L.C.; Wiarda, D.; Jacqmin, R.; Kodeli, I.; ); Chiba, G.; Shibata, K.; Ishikawa, M.; Oh, S.; Nikolaev, M.; Kahler, A.C. Jr.; Kawano, T.; Arcilla, R.

2014-01-01

A Working Party on International Evaluation Co-operation (WPEC) 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. 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), JEF/EFF (NEA Data Bank member countries), and JENDL (Japan). Cooperation with evaluation projects of non- OECD countries is organized through the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report summarizes the work performed by WPEC Subgroup 28 (SG28) on issues pertinent to the methodology used to process covariance data in the resonance region. Specifically, SG28 has developed the requisite processing methods needed to process resonance parameter covariance data, generate cross-section covariance data files and demonstrate the use of covariance data in radiation transport analyses. The work performed by SG28 and documented in this report addresses the following tasks: - Produce resonance parameter covariance evaluation for 235 U; - Develop resonance parameter covariance processing methods in widely used processing systems (e.g., NJOY, AMPX, etc.); - Use the updated cross-section processing systems to generate covariance data files for use in radiation transport analyses. In addition, use sensitivity/uncertainty (S/U) analyses to demonstrate the propagation of the covariance data in specific radiation transport applications

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.

A video automated system for nuclear data in the ENDF format

International Nuclear Information System (INIS)

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

1992-01-01

This paper presents a video catalogue for libraries in the ENDF-5 or ENDF-6 format (Evaluated Nuclear Data File) which can be run on an IBM-PC computer. This user friendly catalogue is of interest to nuclear and reactor physics researchers. The input is the filename of ENDF data and the output two files giving: a) the list of materials with corresponding laboratory, author and date of evaluation: b) uncorresponding about the MF and MT numbers for each material. The program is written in the C language whose capability of providing windows and interrupts along with speed and portability, has been greatly exploited. The system allows output of options (a) and (b) either on screen, printer or hard disk. (author)

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.

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.

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

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.)

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.

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

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

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

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.

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

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

RRDF-98. Russian reactor dosimetry file. Summary documentation

Energy Technology Data Exchange (ETDEWEB)

Pashchenko, A B

1999-03-01

This document summarizes the contents and documentation of the new version of tile Russian Reactor Dosimetry File (RRDF-98) released in December 1998 by the Russian Center on Nuclear Data (CJD) at the Institute of Physics and Power Engineering, Russian Federation. This file contains the original evaluations of cross section data and covariance matrixes for 22 reactions which are used for neutron flux dosimetry by foil activation. The majority of the evaluations included in previous versions of the Russian Reactor Dosimetry Files (BOSPOR-80, RRGF-94 and RRDF-96) have been superseded by new evaluations. The evaluated cross sections of RRDF-98 averaged over 252-Cf and 235-U fission spectra are compared with relevant integral data. The data file is available from the IAEA Nuclear Data Section on diskette, cost free. (author) 9 refs, 22 figs, 2 tabs

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

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)

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

Reminiscences of the U.S. program for applied nuclear data

International Nuclear Information System (INIS)

Pearlstein, S.

1998-01-01

United States industry had developed reliable, sometimes proprietary, systems for thermal reactor design. In 1966, the US Atomic Energy Commission organized a nuclear data effort as part of breeder reactor technology. It was planned that this data technology would be valid in other applications as well. This application independent data library is called Evaluated nuclear Data File (ENDF/B) and is overseen by the Cross Section Evaluation Working Group (CSEWG). Many iterations of ENDF/B have occurred in the effort to achieve an application independent data library. The latest version, EnDF/B-VI, was issued in 1990. Updates to ENDF/B are issued from time-to-time

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

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

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)

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

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

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

The JEFF-3.1 Nuclear Data Library - JEFF Report 21

International Nuclear Information System (INIS)

Koning, Arjan; Forrest, Robin; Kellett, Mark; Mills, Robert; Henriksson, Hans; Rugama, Yolanda; Bersillon, O.; Bouland, O.; Courcelle, A.; Duijvestijn, M.C.; Dupont, E.; Kopecky, J.; Leichtle, D.; Marie, F.; Mattes, M.; Menapace, E.; Morillon, B.; Mounier, C.; Noguerre, G.; Pereslavtsev, P.; Romain, P.; Serot, O.; Simakov, S.; Tagesen, S.; Vonach, H.; Batistoni, P.; Bem, P.; Gunsing, F.; Pillon, M.; Plompen, A.; Rullhusen, P.; Seidel, K.; Avrigeanu, M.; Avrigeanu, V.; Bauge, E.; Leeb, H.; Lopez Jimenez, M.J.; Bernard, D.; Bidaud, A.; Dagan, R.; Dean, C.; Dos-Santos-Uzarralde, P.; Fischer, U.; Hogenbirk, A.; Jacqmin, R.; Jouanne, C.; Kodeli, I.; Leppanen, J.; Marck, S.C. van der; Perel, R.; Perry, R.; Pescarini, M.; Santamarina, A.; Sublet, J.C.; Trkov, A.; Be, M.M.; Huynh, T.D.; Kellett, M.A.; Mills, R.; Nichols, A.; Henriksson, H.; Nordborg, C.; Nouri, A.; Rugama, Y.; Sartori, E.

2006-01-01

The Joint Evaluated Fission and Fusion (JEFF) Project is a collaborative effort among the member countries of the NEA Data Bank to develop a reference nuclear data library. The JEFF library contains sets of evaluated nuclear data, mainly for fission and fusion applications; it contains a number of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data and photo-atomic interaction data. The latest version of the JEFF library, JEFF-3.1, was released by the NEA in May 2005. JEFF-3.1 combines the efforts of the JEFF and EFF/EAF (European Fusion File/European Activation File) working groups who have contributed to this combined fission and fusion library. The neutron general purpose library contains incident neutron data for 381 materials from 1 H to 255 Fm. The activation library (based on the European Activation File, EAF-2003) contains 774 different targets from 1 H to 257 Fm. The radioactive decay data library contains data for 3 852 isotopes, of which 226 are stable. The proton special purpose library contains incident proton data for 26 materials from 40 Ca to 209 Bi. The thermal scattering law library covers 9 materials, and the fission yield library covers 19 isotopes of neutron induced fission yield from 232 Th to 245 Cm and 3 isotopes with spontaneous fission yields ( 242 Cm, 244 Cm and 252 Cf)

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.)

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

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.

The UK chemical nuclear data library: a summary of the data available in ENDF/B format

International Nuclear Information System (INIS)

Davies, B.S.J.

1981-11-01

The UK Chemical Nuclear Data Committee files have been considerably revised and extended. The files now embrace: fission yields (C31), fission product decay data (UKFPDD-2), activation product decay data (UKPADD-1), and heavy element decay data (UKHEDD-1). The fission yield data is based on Crouch's third round of adjustment and includes yields to isometric states. The decay data files include data on half-life, decay modes, branching ratios and alpha, beta and gamma radiation energies and intensities. The data have all been recommended by the UK Chemical Nuclear Data Committee for use in the UK reactor programme; they are stored on magnetic tape at AERE Harwell, AEE Winfrith and CEGB Berkeley Nuclear Laboratories. (author)

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)

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

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.

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)

Annual report of nuclear code evaluation committee for fiscal 2000 year

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-03-01

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

Nuclear models and data for gamma-ray production

International Nuclear Information System (INIS)

Young, P.G.

1975-01-01

The current Evaluated Nuclear Data File (ENDF/B, Version IV) contains information on prompt gamma-ray production from neutron-induced reactions for some 38 nuclides. In addition, there is a mass of fission product yield, capture, and radioactive decay data from which certain time-dependent gamma-ray results can be calculated. These data are needed in such applications as gamma-ray heating calculations for reactors, estimates of radiation levels near nuclear facilities and weapons, shielding design calculations, and materials damage estimates. The prompt results are comprised of production cross sections, multiplicities, angular distributions, and energy spectra for secondary gamma-rays from a variety of reactions up to an incident neutron energy of 20 MeV. These data are based in many instances on experimental measurements, but nuclear model calculations, generally of a statistical nature, are also frequently used to smooth data, to interpolate between measurements, and to calculate data in unmeasured regions. The techniques and data used in determining the ENDF/B evaluations are reviewed, and comparisons of model-code calculations and ENDF data with recent experimental results are given. 11 figures

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)

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

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

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

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.

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)

PKA spectrum file

Energy Technology Data Exchange (ETDEWEB)

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