The coupled neutron transport calculation of Monte Carlo multi-group and continuous cross section

Autor: Deng, Li, Hu, Zehua, Li, Rui, Cheng, Tangpei, Yang, Chao, Fu, Yuangang, Shi, Dunfu, Li, Gang, Zhang, Baoyin, Zhang, Lingyu, Wen, Lili
Zdroj: In Annals of Nuclear Energy May 2019 127:433-436
Databáze: ScienceDirect