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Book The Status of Nuclear Data Evaluations for Version VI of ENDF

Download or read book The Status of Nuclear Data Evaluations for Version VI of ENDF written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A new version of the United States national evaluated nuclear data file, ENDF/B-VI, is nearing completion. Major emphasis is being placed on correcting some long-standing nuclear data problems that adversely affect applied calculations for fission and fusion reactors. This paper reviews some of the evaluation activities of most revelance for fission reactor applications, namely, those involving control, cooling, and shielding materials, structural elements, and the major actinides. Additionally, because of its impact on all the data, work on the Standards Data File for Version VI is also summarized.

Book The Status of ENDF B VI

Download or read book The Status of ENDF B VI written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A new version of the United States evaluated nuclear data file, ENDF/B-VI, is presently under development. Major emphasis is being placed on correcting some long-standing nuclear data problems that adversely affect applied calculations for both fission and fusion reactors. The paper reviews modifications to the formats and utility codes, outlines the evaluation activities, discusses the data testing programs, and projects a date for the unrestricted release of the new library. 27 refs., 2 tabs.

Book Godsdienstige bijeenkomst

Download or read book Godsdienstige bijeenkomst written by and published by . This book was released on 1930 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Status of ENDF

    Book Details:
  • Author :
  • Publisher :
  • Release : 1988
  • ISBN :
  • Pages : pages

Download or read book The Status of ENDF written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A new version of the United States evaluated nuclear data file, ENDF/B-VI, is presently under development. Major emphasis is being placed on correcting some long-standing nuclear data problems that adversely affect applied calculations for both fission and fusion reactors. The paper reviews modifications to the formats and utility codes, outlines the evaluation activities, discusses the data testing programs, and projects a date for the unrestricted release of the new library. 27 refs., 2 tabs.

Book Status of Nuclear Data of Importance for LMFBR Applications Prior to the Evaluation of ENDF

Download or read book Status of Nuclear Data of Importance for LMFBR Applications Prior to the Evaluation of ENDF written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The evaluation of nuclear data of importance to the LMFBR program has shifted to a Nuclear Data Evaluation Task Force. It is anticipated that the results of these evaluations will be incorporated in ENDF/B-VI. However, several cross sections for reactor applications are included in a simultaneous evaluation of the standard cross sections for ENDF/B-VI organized by the Standard Subcommittee of CSEWG. Cross sections included in this simultaneous evaluation are those of 6Li(n, .cap alpha.), 6Li(n, n), 1°B(n, .cap alpha.0), 1°B(n, .cap alpha.1), 1°B(n, n), 197Au(n, .gamma.), 235U(n, f), 238U(n, .gamma.), 238U(n, f), and 239Pu(n, f). The change of the evaluation methodology for ENDF/B-VI will result in a much improved definition of the data, their uncertainties and cross correlations. Trends which can be seen in new data and which are caused by the change of the evaluation procedure are toward, lower 239Pu(n, f), 235U(n, .gamma.), modestly lower 235U(n, f), and higher 1°B(n, .cap alpha.) data. The data base for 238U(n, .gamma.) below 30 keV remains poorly defined and a resolution of the C/E discrepancy of C28/F49 cannot be expected from the infinite dilute capture cross section of 238U. Anti nu of 252Cf remains unchanged and therefore also the nu(E) of the fissile isotopes, except at thermal energy.

Book Nuclear Data Evaluation Methodology   Proceedings Of The International Symposium

Download or read book Nuclear Data Evaluation Methodology Proceedings Of The International Symposium written by C L Dunford and published by World Scientific. This book was released on 1993-08-12 with total page 756 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Symposium on Nuclear Data Evaluation Methodology provided a forum for the discussion of developments made over the past 12 years in the evaluation methods used for generating data files for applied technology. With a program that was prepared by an international committee of experts in this field, this set of proceedings gives a comprehensive overview of the development and progress of this field for the last 12 years. It serves as an important source of reference and historical update for those seeking an in-depth understanding of this study.

Book ENDF B VI Nuclear Data Evaluations for Fusion Applications

Download or read book ENDF B VI Nuclear Data Evaluations for Fusion Applications written by and published by . This book was released on 1988 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book General Purpose Nuclear Data Evaluations for ENDF

Download or read book General Purpose Nuclear Data Evaluations for ENDF written by and published by . This book was released on 1990 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past year the Cross Section Evaluation Working Group (CSEWG) has finalized and issued new evaluations for over 70 nuclides in Version 6 of ENDF/B. These data provide the foundation for a new series of reactor benchmark calculations. An integral part of the evaluation effort for ENDF/B-VI has been the most ambitious effort ever undertaken to systematically and simultaneously reevaluate the cross sections used for neutron standards. While a number of the materials and reactions identified as standards are directly involved in fission reactor calculations, the impact of the standards data is felt far beyond the specific standards reactions. The effect of the Version 6 standards data file on several evaluations of data of interest for fission reactors is discussed in this paper, together with the methodology used to utilize the standards.

Book ENDF 102 DATA FORMATS AND PROCEDURES FOR THE EVALUATION NUCLEAR DATA FILE ENDF 6

Download or read book ENDF 102 DATA FORMATS AND PROCEDURES FOR THE EVALUATION NUCLEAR DATA FILE ENDF 6 written by and published by . This book was released on 2001 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book ENDF 201

    Book Details:
  • Author :
  • Publisher :
  • Release : 1991
  • ISBN :
  • Pages : 473 pages

Download or read book ENDF 201 written by and published by . This book was released on 1991 with total page 473 pages. Available in PDF, EPUB and Kindle. Book excerpt: Responsibility for oversight of the ENDF/B Evaluated Nuclear Data file lies with the Cross Section Evaluation Working Group (CSEWG), which is comprised of representatives from various governmental and industrial laboratories in the United States. Individual evaluations are provided by scientists at several US laboratories, including significant contributions by scientists from all over the world. In addition, ENDF/B-VI includes for the first time complete evaluations for three materials that were provided from laboratories outside the US. All data are checked and reviewed by CSEWG, and the data file is maintained and issued by the National Nuclear Data Center at Brookhaven National Laboratory. The previous version of the library, ENDF/B-V, was issued in 1979, and two revisions to the data file were provided in subsequent years, the latest occurring in 1981. A total of 75 new or extensively modified neutron sublibrary evaluations are included in ENDF/B-VI, and are summarized in this document. One incident proton sublibrary is described for Fe56. The remaining evaluations in ENDF/B-VI have been carried over from earlier versions of ENDF, and have been updated to reflect the new formats. The release of ENDF/B-VI was carried out between January and June of 1990, with groups of materials being released on ''tapes.'' Table 1 is an index to the evaluation summaries, and includes the material identification or MAT number, the responsible laboratory, and the ''tape'' number. These evaluations have been released without restrictions on their distribution or use.

Book ENDF 201  ENDF

    Book Details:
  • Author :
  • Publisher :
  • Release : 1996
  • ISBN :
  • Pages : 267 pages

Download or read book ENDF 201 ENDF written by and published by . This book was released on 1996 with total page 267 pages. Available in PDF, EPUB and Kindle. Book excerpt: The National Nuclear Data Center (NNDC) provides coordination for and serves as the secretariat to the Cross Section Evaluation Working Group (CSWEG). CSEWG is responsible for the oversight of the ENDF/B Evaluated Nuclear Data File. All data are checked and reviewed by CSEWG, and the file is maintained at the NNDC. For a description of the ENDF/B-VI file, see the ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6. The purpose of this addendum to the ENDF/B-VI Summary Documentation is to provide documentation of Releases 1, 2, 3, and 4 for the ENDF/B-VI and ENDF/HE-VI evaluated nuclear data libraries. These releases contain many new and revised evaluations for the neutron, photo-atomic interaction, radioactive decay data, spontaneous fission product yield, neutron-induced fission product yield, thermal neutron scattering, proton, deuteron, and triton sublibraries. The summaries have been extracted mainly from the ENDF/B-VI File 1 comments (MT = 451), which have been checked, edited, and may also include supplementary information. Some summaries have been provided by the evaluators in electronic format, while others are extracted from reports on the evaluations. All references have been checked and corrected, or updated where appropriate. A list of the laboratories which have contributed evaluations used in ENDF/B-VI is given.

Book ENDF B VI Nuclear Data Evaluations for Fusion Applications

Download or read book ENDF B VI Nuclear Data Evaluations for Fusion Applications written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The next release of the ENDF/B data library planned for 1989 contains improved data evaluations of interest to the fusion neutronics community. New data formats permit inclusion of energy-angle correlated particle emission spectra and recoil nucleus energy spectra. Enhanced formats for covariance information have been developed. Many new isotopic evaluations will lead to improved energy conservation and kerma factor calculations. Improved nuclear model calculations will provide reliable particle emission data where experimental information is sparse. Improved Bayssian fitting codes will provide more accurate evaluations for data rich reactions such as Li(n, nt)..cap alpha ... All of the most important fusion material evaluations contain these new features. 32 refs., 8 figs.

Book Evaluated Nuclear Data File ENDF

Download or read book Evaluated Nuclear Data File ENDF written by and published by . This book was released on 1991 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: For the past 25 years, the United States Department of Energy has sponsored a cooperative program among its laboratories, contractors and university research programs to produce an evaluated nuclear data library which would be application independent and universally accepted. The product of this cooperative activity is the ENDF/B evaluated nuclear data file. After approximately eight years of development, a new version of the data file, ENDF/B-VI has been released. The essential features of this evaluated data library are described in this paper. 7 refs.

Book Recent Advances in the US Fission Yield and Delayed Neutron Evaluations

Download or read book Recent Advances in the US Fission Yield and Delayed Neutron Evaluations written by and published by . This book was released on 1992 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past fifteen years, US reactor analysts have been presented with three major evaluated nuclear data bases: Evaluated Nuclear Data Files (ENDF/B) versions -IV, -V, and most recently, -VI. Advances in the quantity and quality of fission yield data have been almost exponential from evaluation to evaluation. The most recent release of ENDF/B-VI represents an entirely new approach to the evaluation of delayed neutron data. Due to the effort and expense of processing and testing the basic data evaluations for specific applications, data libraries contained in the m mn reactor physics codes are not usually dated with the release of a new evaluation. This is particularly true for the decay data files utilizing fission yield and delayed neutron data. The introduction of ANSI/ANS standards for data of this type would provide a mechanism for assuring the reliability and quality of data of this type. Working groups for each of these proposed standards are comprised of both US and international experts in areas of reactor physics utilizing these data, as well as the data evaluators themselves. This summary briefly discusses the status of the two data evaluations and the progress toward developing standards in each area.

Book ENDF 6 Formats Manual Data Formats and Procedures for the Evaluated Nuclear Data File ENDF

Download or read book ENDF 6 Formats Manual Data Formats and Procedures for the Evaluated Nuclear Data File ENDF written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.