ENDF/B Summary Documentation

Abstract

INTRODUCTIONThe purpose of this publication is to provide a localized source of descriptions for the evaluations contained in the ENDF/B Library.The summary documentation presented in this volume is intended to be a more detailed description than the (File 1) comments contained in the computer readable data files, but not as detailed as the formal reports describing each ENDF/B evaluation. (A list of the published formal reports is given in the table of contents.)The summary documentations were written by the CSEWG (Cross Section Evaluation Working Group) evaluators and compiled by NNCSC (National Neutron Cross Section Center). When assembling the information for this volume, a minimum amount of editing was unavoidable. This editing primarily consisted of removing computer file listings and irreproducible graphs, since these can be easily obtained from the ENDF files with the use of standard editing or plotting programs. In a few instances, sections of the formal document were reproduced. Materials for which no summary documentation has been received to date, are represented by the (File 1) comments contained in the data file only.The loose leaf"independent section format was selected for ease of updating when more documentation and/or evaluations become available. It is hoped that In the future a more standardized documentation will make the updating simplified.The publication is presented in sections, each section describing one (or more) ENDF evaluations. These sections are identified and ordered by element number (Z) and atomic weight (A). Sections describing more than one ENDF material are identified by the Z-A numbers of the lowest material described. The section number corresponding to a particular data set should be determined using the table of contents.(e.g., s Li(HAT-1115) is described in Section 3-6, whereas 1S3 Cs(MAT-1141) is described in Section 47-107, which also includes 107 Ag and 10S Ag.)The ENDF/B-III Library contains 230 materials. (A material may consist of an isotope, element, molecule, or standard mixture of elements.) Ten of these materials contain thermal scattering law data only. Eightyseven materials consist of photon interaction cross sections for elements. The summary documentations presented in this volume describe the principal part of the library consisting of the remaining 133 materials with neutron cross sections specified for all relevant reactions.The documentation for a number of "lumped" fission product materials is given following the section of the corresponding fissionable material. 1-H-1 1-H-2 2-HE 2-HE-3 3-LI-6 3-LI-7 4-BE-9 S-S-10 S-B-11 6-C-12 7-N-14 8- 29-CU 29-CU-63 29-CU-65 36-KR-83 40-ZR-95 41-NB-93 41-NB-95 42-MO 42-MO-95 42-MO-97 42-M0-98 42-MO-99 42-MO-10© 43-TC-99 44-RU-101 44-RU-102 44-RU-103 44-RU-104 44-RU-105 44-RU-106 45-RH-1O3 45-RH-10S 46-PD-105 46-PD-106 46-PD-107 46-PD-109 47-AC-107 47-AG-109 48-CD-113 S3-1-131 53-1-135 S4-XE-131 S4-XE-133 54-XE-13S 55-CS-133 S5-CS-135 S5-CS-137 57-LA-139 'S8-CE- Because of ...

The nuclear performance of vanadium as a structural material infusion reactor blankets

“…The neutron cross-sections of 6 Li, 7 Li, 12 C, and 93 Nb were taken from ENDF/B, version III [10]. The vanadium cross-sections came from Ref.…”