Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX

Author:

Wu Hongchun,Qin Shuai,Li Yunzhao,Shi Jinkang,He QingmingORCID,Cao LiangzhiORCID

Publisher

Elsevier BV

Reference28 articles.

1. Multigroup Cross Section Generation via Monte Carlo Methods;Redmond,1997

2. Application of continuous-energy Monte Carlo code as a cross-section generator of BWR core calculations;Tohjoh;Ann. Nucl. Energy,2005

3. Generation of multi-group cross sections and scattering matrices with the Monte Carlo code MCNP5;Hoogenboom,2007

4. On the use of the Serpent Monte Carlo code for few-group cross section generation;Fridman;Ann. Nucl. Energy,2011

5. Generation of few-group diffusion theory constants by Monte Carlo code McCARD;Park;Nucl. Sci. Eng.,2012

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