摘要
MCFT是计算快、热中子多群常数的计算程序。作为程序输入的基本核数据库可以具有不同的格式。程序可以处理共振截面的公式和各种热化模型的散射律数据。输出结果的适用范围较广。
MCFT is a program for calculating the fast and thermal neutron multigroup constants, which is redesigned from the code^([2]) for generation of thermal neutron multigroup constants and the code^([3]) for fast neutron multigroup constants adapted on CYBER 825 computer. It uses indifferently as basic input the evaluated nuclear data contained in the ENDF/B (US), KEDAK (Germany) and UK (United Kingdom) libraries. The code includes a section devoted to the generation of resonant Doppler broadened cross section in the framework of single-or multi-level Breit-Wigner formalism. The program can compute the thermal neutron scattering law S(α,β,T) as the input data in tabular, free gas or diffusion motion form, and treat up to 200 energy groups and Legendre moments up to P_5. The output consists of various reaction multigroup constants in all neutron energy range desired in the nuclear reactor design and calculation. Three options in input file can be used by the user, option=1, fast neutron multigroup constants generation only, = 2, thermal neutron multigroup constants generation only, = 3, fast and thermal neutron multigroup constant generation. The output format is arbitrary and defined by user with a minimum of program modification. The program includes about 15,000 cards and 184 subroutines. FORTRAN 5 computer language is used. The operation system is under NOS 2 on computer CYBER 825 (in China Institute of Atomic Energy).
出处
《核科学与工程》
CSCD
北大核心
1993年第2期143-147,7,共5页
Nuclear Science and Engineering
