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Endf 102 Data Formats And Procedures For The Evaluation Nuclear Data File Endf 6
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Book Synopsis ENDF-102 DATA FORMATS AND PROCEDURES FOR THE EVALUATION NUCLEAR DATA FILE ENDF-6 by :
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 Synopsis ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6. Revision November 1995 by :
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 Synopsis ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6 by :
Download or read book ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6 written by and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File, ENDF by :
Download or read book ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File, ENDF written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Synopsis ENDF-201, ENDF/B-VI Summary Documentation Supplement 1, ENDF/HE-VI Summary Documentation by :
Download or read book ENDF-201, ENDF/B-VI Summary Documentation Supplement 1, ENDF/HE-VI Summary Documentation 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 Synopsis ENDF-6 Formats Manual Data Formats and Procedures for the Evaluated Nuclear Data File ENDF by :
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 Synopsis Nuclear Data for Science and Technology by : Syed M. Qaim
Download or read book Nuclear Data for Science and Technology written by Syed M. Qaim and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 1041 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes the Proceedings of the International Conference on Nuclear Data for Science and Technology held at Jillich in May 1991. The conference was in a series of application oriented nuclear data conferences organized in the past under the auspices of the Nuclear Energy Agency-Nuclear Data Committee (NEANDC) and with the support of the Nuclear Energy Agency-Committee on Reactor Physics (NEACRP). It was the fIrst international conference on nuclear data held in Germany, with the scientific responsibility entrusted to the Institute of Nuclear Chemistry of the Research Centre Jillich. The scientific programme was established by the International Programme Committee in consultation with the International Advisers, and the NEA and IAEA cooperated in the organization. A total of 328 persons from 37 countries and fIve international organizations participated. The scope of these Proceedings extends to a wide range of interdisciplinary topics dealing with measu rement, calculation, evaluation and application of nuclear data, with a major emphasis on numerical data. Both energy and non-energy related applications are considered and due attention is given to some fundamental aspects relevant to the understanding of nuclear data.
Book Synopsis Nuclear Data Evaluation Methodology - Proceedings Of The International Symposium by : C L Dunford
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 Synopsis Nuclear Reaction Data And Nuclear Reactors - Physics, Design And Safety: Proceedings Of The Workshop by : Pavol Oblozinsky
Download or read book Nuclear Reaction Data And Nuclear Reactors - Physics, Design And Safety: Proceedings Of The Workshop written by Pavol Oblozinsky and published by World Scientific. This book was released on 1999-07-22 with total page 550 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume provides the up-to-date information behind nuclear reactor calculations, focusing on a key role of nuclear reaction data, down to the physics of nuclear interactions. It is divided into three parts. Part 1 deals with nuclear reaction models, including neutron resonances, fission, the optical model, statistical and preequilibrium models as well as nuclear level densities. Part 2 is devoted to nuclear data filling and processing; it includes lectures on nuclear data evaluation and formatting, data libraries and services, with emphasis on nuclear-data-processing codes. Part 3 presents applications in nuclear reactor calculations, emphasizing physics, design and safety.
Book Synopsis Data formats and procedures for the evaluated nuclear data file, endf by : P. F. Rose
Download or read book Data formats and procedures for the evaluated nuclear data file, endf written by P. F. Rose and published by . This book was released on 1988 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Status of Nuclear Data Evaluations for Version VI of ENDF by :
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.
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.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Synopsis Reactor Physics Calculations For Applications In Nuclear Technology - Proceedings Of The Workshop by : Dermott E Cullen
Download or read book Reactor Physics Calculations For Applications In Nuclear Technology - Proceedings Of The Workshop written by Dermott E Cullen and published by World Scientific. This book was released on 1991-01-30 with total page 757 pages. Available in PDF, EPUB and Kindle. Book excerpt: This workshop was designed to meet the needs of those currently involved in or are planning a nuclear programme involving research and/or power fission reactors. The workshop had a broad scope including not only fission reactor core calculations, but also safety, fuel management, waste disposal reactor licensing. The lectures and computer exercises covered almost all aspects of the operation of fission reactors.This workshop introduced participants to the methods currently used in fission reactor calculations and to some computer codes in which these methods are used.
Book Synopsis Computation And Analysis Of Nuclear Data Relevant To Nuclear Energy And Safety by : M K Mehta
Download or read book Computation And Analysis Of Nuclear Data Relevant To Nuclear Energy And Safety written by M K Mehta and published by World Scientific. This book was released on 1993-12-16 with total page 946 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book focuses on the modern nuclear models and computer codes used in nuclear model calculations of nuclear data required for nuclear technology and nuclear safety applications.
