Download or read book Evaluations of Fission Product Capture Cross Sections for ENDF B V written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Capture cross section evaluations were made for the 36 most important fission product absorbers in a fast reactor system. These evaluations were obtained by use of a generalized least-squares approach with calculations being performed with the computer code FERRET. These results will provide the major revisions to the ENDF/B-IV Fission Product Cross Section File which will be released as part of ENDF/B-V. Input for the cross section adjustment calculations included both integral and differential experimental data results. The differential cross sections and their uncertainties were obtained from the CSIRS library. Integral measurement results came from CFRMF and STEK Assemblies 500, 1000, 2000, 3000, and 4000. Comparisons of these evaluations with recent capture measurements are presented. 14 figures.

Download or read book ENDF B 5 Fission Product Cross Section Evaluations written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files. Most of the evaluations involve updating the capture cross sections of the important absorbers for fast and thermal reactor systems. This included updating thermal values, resonance integrals, resonance parameter sets, and fast capture cross sections. For the fast capture results generalized least-squares calculations were made with the computer code FERRET. Input for these cross section adjustments included nuclear models calculations and both integral and differential experimental data results. The differential cross sections and their uncertainties were obtained from the CSIRS library. Integral measurement results came from CFRMF and STEK Assemblies 500, 1000, 2000, 3000, 4000. Comparisons of these evaluations with recent capture measurements are shown. 15 figures, 10 tables.

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.

Download or read book Statistical Evaluation of Fission product Absorption Cross Sections at Intermediate and High Energies written by P. Greebler and published by . This book was released on 1956 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of the Fission and Capture Cross Sections of sup 240 sup Pu and sup 241 sup Pu for ENDF B V 10 sup 5 EV to 20 MeV written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Since there were appreciable new data which were not available for ENDF/B-IV, new evaluations for /sup 240/Pu and /sup 241/Pu were carried out for ENDF/B-V. The evaluation of the fission and capture cross sections is reviewed and problem areas are discussed. The neutron energy range of concern was from 10/sup -5/ eV to 20 MeV. Significant changes were made over the entire neutron energy region because of the new experimental data available. The problems in the evaluations due to discrepancies in the nuclear data are emphasized, particularly the 1-eV resonance in /sup 240/Pu and the 0.3-eV resonance in /sup 241/Pu. The evaluation of the fission and capture cross sections for ENDF/B-V represents an improvement over the previous evaluation; however, there continues to be a need for accurate experimental data. 7 figures.

Download or read book Agenda as Adopted at the 3rd and 5th Meetings on 8 and 11 April 1980 written by and published by . This book was released on 1980 with total page 2 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of the Fission and Capture Cross Sections of 24 Pu and 241Pu for ENDF written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Since there were appreciable new data which were not available for ENDF/B-IV, new evaluations for 24°Pu and 241Pu were carried out for ENDF/B-V. The evaluation of the fission and capture cross sections is reviewed and problem areas are discussed. The neutron energy range of concern was from 10−5 eV to 20 MeV. Significant changes were made over the entire neutron energy region because of the new experimental data available. The problems in the evaluations due to discrepancies in the nuclear data are emphasized, particularly the 1-eV resonance in 24°Pu and the 0.3-eV resonance in 241Pu. The evaluation of the fission and capture cross sections for ENDF/B-V represents an improvement over the previous evaluation; however, there continues to be a need for accurate experimental data. 7 figures.

Download or read book Review of ENDF B VI Fission Product Cross Sections Evaluated Nuclear Data File written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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).

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.

Download or read book NBS Special Publication written by and published by . This book was released on 1968 with total page 1064 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Cross Sections and Technology written by Roald Amundsen Schrack and published by . This book was released on 1975 with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of Fission Cross Sections and Covariances 233U 235U 238U 239Pu 240Pu and 241Pu written by and published by . This book was released on 2000 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Revised Evaluations for ENDF written by and published by . This book was released on 1993 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this paper is to report on revised cross-section evaluations for 17 nuclides that have been prepared for ENDF/B-VI Revision 2. The nuclides considered include five fission products and various isotopes of cadmium and hafnium. The previous ENDF/B-VI evaluations for these 17 nuclides were carried over from ENDF/B-V and were completed in the 1974--1980 time period. By utilizing the experimental data that have become available since 1980 the revised evaluations will result in significant improvements in the evaluated nuclear data files. The primary emphasis was placed on the resolved and unresolved resonance regions, but new experimental data were also used to improve the cross sections for energies above the unresolved resonance region. Negative elastic scattering cross sections were encountered in some of the previous evaluations; since the revised evaluations use multilevel Breit-Wigner (MLBW) parameters, rather than single-level Breit-Wigner (SLBW), this problem is eliminated.

Download or read book Impact of Integral Measurements on the Capture Cross Section Evaluations of Individual Fission Product Isotopes written by Harm Gruppelaar and published by . This book was released on 1977 with total page 65 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Intercomparison of Recent Evaluations for the Capture Cross Sections of Some Fission product Nuclides written by H. Gruppelaar and published by . This book was released on 1976 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of Neutron and Gamma ray production Cross Sections for Natural Iron ENDF B V MAT 1326 written by and published by . This book was released on 1980 with total page 41 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Updates to the ORIGEN S Cross Section Libraries Using ENDF VI EAF 99 and FENDL 2 0 written by B. D. Murphy and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The standard cross-section library for light-water reactor (LWR) analyses used by the ORIGEN-S depletion and decay code has been extensively updated. This work entailed the development of broad multigroup neutron cross sections for ORIGEN-S from several sources of pointwise continuous-energy cross-section evaluations, including the U.S. Evaluated Nuclear Data Files ENDF/B-VI Release 7, the Fusion Evaluated Nuclear Data Library FENDL-2.0, and the European Activation File EAF-99. The pointwise cross sections were collapsed to a three-group structure using a continuous-energy neutron flux spectrum representative of the typical neutronic conditions of typical LWR fuel and formatted for use by ORIGEN-S. In addition, the fission-product library has been expanded to include ENDF/B-VI fission yield data for 30 fissionable actinides. The processing codes and procedures are explained. Preliminary verification studies using the updated libraries were performed using the modules of the SCALE (Standardized Computer Analyses for Licensing Evaluation) system. Comparisons between the previous basic ORIGEN-S libraries and the updated libraries developed in this work are presented.