Subject
Nuclear Energy and Engineering
Reference24 articles.
1. On the use of the serpent Monte Carlo code for few-group cross section generation;Fridman;Ann. Nucl. Energy,2011
2. A Procedure for Obtaining Neutron Diffusion Coefficients from Neutron Transport Monte Carlo Calculations;Gast,1981
3. Monte Carlo calculation of the diffusion coefficient of nuclear reactor cells;Gorodkov;At. Energy,2009
4. Problem-dependent Doppler broadening of continuous-energy cross sections in the KENO Monte Carlo computer code;Hart,2014
5. A consistent technique for the global homogenization of a pressurized water reactor assembly;Hébert;Nucl. Sci. Eng.,1991
Cited by
1 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献