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Book Special Issue on Evaluated Nuclear Data File ENDF B VII 1 Library

Download or read book Special Issue on Evaluated Nuclear Data File ENDF B VII 1 Library written by P. Obložinský and published by . This book was released on 2011 with total page 3 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Special Issue on Evaluated Nuclear Data File ENDF B VII 0

Download or read book Special Issue on Evaluated Nuclear Data File ENDF B VII 0 written by P. Obložinský and published by . This book was released on 2006 with total page 187 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Release of the ENDF B VII  1 Evaluated Nuclear Data File

Download or read book Release of the ENDF B VII 1 Evaluated Nuclear Data File written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

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 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

    Book Details:
  • Author : Henry C. Honeck
  • Publisher :
  • Release : 1967
  • ISBN :
  • Pages : 118 pages

Download or read book ENDF B written by Henry C. Honeck and published by . This book was released on 1967 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book ENDF

    Book Details:
  • Author :
  • Publisher :
  • Release : 1994
  • ISBN :
  • Pages : 53 pages

Download or read book ENDF written by and published by . This book was released on 1994 with total page 53 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear and atomic data are the foundation upon which the radiation transport codes are built. For neutron transport the international standard is the Evaluated Nuclear Data File from Brookhaven National Laboratory. The latest version, ENDF/B-VI release 2, has recently become available for use in the Monte Carlo N-Particle (MCNP) radiation transport code. These neutron cross-section data are designated by ZAID identifiers ending in .60c and are referred to as the ENDF60 library. The ENDF60 data library was processed from the ENDF/B-VI evaluations using the NJOY code. Fifty-two percent of the data evaluations are translations from ENDF/B-V. The remaining 48% are new evaluations which have sometimes changed significantly. The RSIC release package contains the ENDF60 neutron library, a new photon library MCPLIB02, the electron library EL1, and an updated XSDIR file. The authors report here the work done by the LANL Radiation Transport Group (X-6) in testing and validating the ENDF60 data library and in developing the necessary new sampling and detector schemes. When the ENDF60 library should be used in preference to the previous libraries, is also considered. The development of the new photon library MCPLIB02 is also discussed.

Book ENDF B VII  1 Versus ENDF B VII 0

Download or read book ENDF B VII 1 Versus ENDF B VII 0 written by and published by . This book was released on 2012 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recently the new ENDF/B-VII. 1 library was released; this completely replaces the earlier ENDF/B-VII.0 library. One of the first questions we ask about a new library is: What's Different? Here I attempt to at least partially answer this question. I present results in both tabulated form (so you can quickly determine if any evaluations of interest to you have changed), and graphic form (so that you can see how much evaluations have changed and in what energy ranges). For the table I have compared what I refer to as the ENDF neutron data, namely MF=1 through 6. Here I did a character-by-character comparison of the same sections (MF/MT) that appear I both ENDF/B-VII.0 and VII. 1; here I found differences in 170 evaluations. For the plots I have only compared the total cross sections for all evaluations that are common to both libraries, and I found that of the 423 evaluations in ENDF/B-VII. 1, 120 of these have total cross sections that differ by 1% or more from the evaluation of the same isotope in ENDF/B-VII.0. This should be considered only a preliminary comparison; obviously there can be more subtle important differences that do not effect of total cross sections. Here I present plots comparing the total cross section of these 120 isotopes. The plots are only broad overviews of the total cross sections over their entire energy range. If you have interest in more detailed plots for specific evaluations, you can download the evaluations [1,2] and the PREPRO [3] codes I used to prepare and view the data. This is all I needed to do my comparisons, and is all you should need to do any more detailed comparisons to meet your individual needs.

Book Development of ENDF B VII  1 and Its Covariance Component

Download or read book Development of ENDF B VII 1 and Its Covariance Component written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US nuclear data community, coordinated by CSEWG, is preparing release of the ENDF/B-VII. 1 library. This new release will address deficiencies identified in ENDF/B-VII.0, include improved evaluations for some 50-60 materials and provide covariances for more than 110 materials. The major players in this undertaking are LANL, BNL, ORNL, and LLNL. We summarize deficiencies in the ENDF/B-VII.0 and outline development of the new library. We concentrate on the BNL activities which aim in providing covariances for the materials important for the design of the innovative reactors. Finally we outline a futuristic approach, known as assimilation that tries to link nuclear reaction theory and integral experiments.

Book ENDF 102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF 6  Revision November 1995

Download or read book ENDF 102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF 6 Revision November 1995 written by and published by . This book was released on 1995 with total page 314 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

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 Special Issue on Nuclear Reaction Data

Download or read book Special Issue on Nuclear Reaction Data written by and published by . This book was released on 2012 with total page 330 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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.

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 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.