Extended development of a Monte Carlo code OpenMC for fuel cycle simulation of molten salt reactor
Zhuang, Kun, Li, Ting, Zhang, Qian, He, Qinghua, Zhang, TengfeiVolume:
118
Journal:
Progress in Nuclear Energy
DOI:
10.1016/j.pnucene.2019.103115
Date:
January, 2020
File:
PDF, 3.06 MB
2020