MENDF71x. Multigroup Neutron Cross Section Data Tables Based upon ENDF/B-VII.1

Conlin, Jeremy Lloyd¹  Parsons, Donald Kent¹  Gardiner, Steven J.²  Gray, Mark Girard¹  Lee, Mary Beth¹  White, Morgan Curtis¹ 

[1] Los Alamos National Lab. (LANL), Los Alamos, NM (United States);Univ. of California, Davis, CA (United States)

关键词: NUCLEAR DATA COLLECTIONS;    EVALUATED DATA;    TEMPERATURE RANGE 0273-0400 K;    CROSS SECTIONS;    EXCITED STATES;    GROUND STATES;    MULTIGROUP THEORY;    NEUTRON REACTIONS;   

DOI  :  10.2172/1233259
RP-ID  :  LA-UR--15-29571
PID  :  OSTI ID: 1233259
Others  :  TRN: US1600191

学科分类：核物理和高能物理

美国|英语

来源: SciTech Connect

【 摘 要 】

A new multi-group neutron cross section library has been released along with the release of NDI version 2.0.20. The library is named MENDF71x and is based upon the evaluations released in ENDF/B-VII.1 which was made publicly available in December 2011. ENDF/B-VII.1 consists of 423 evaluations of which ten are excited states evaluations and 413 are ground state evaluations. MENDF71x was created by processing the 423 evaluations into 618-group, downscatter only NDI data tables. The ENDF/B evaluation files were processed using NJOY version 99.393 with the exception of ³⁵Cl and ²³³U. Those two isotopes had unique properties that required that we process the evaluation using NJOY version 2012. The MENDF71x library was only processed to room temperature, i.e., 293.6 K. In the future, we plan on producing a multi-temperature library based on ENDF/B-VII.1 and compatible with MENDF71x.