Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods

RMC – A Monte Carlo code for reactor core analysis

Kan Wang, Zeguang Li, Ding She et al. · Annals of Nuclear Energy · 2014 · 354 citations

Engineering, Nuclear Engineering, Physics +14

Development of burnup methods and capabilities in Monte Carlo code RMC

Ding She, Yuxuan Liu, Kan Wang et al. · Annals of Nuclear Energy · 2012 · 59 citations

Computing, Computer Science, Computational Physics +9

Studies of fuel loading pattern optimization for a typical pressurized water reactor (PWR) using improved pivot particle swarm method

Shichang Liu, Jiejin Cai · Annals of Nuclear Energy · 2012 · 42 citations

Engineering, Computational Engineering, Nuclear Engineering +16

2D full-core Monte Carlo pin-by-pin burnup calculations with the RMC code

Ding She, Jingang Liang, Kan Wang et al. · Annals of Nuclear Energy · 2013 · 23 citations

Engineering, Nuclear Engineering, Physics +7

Neutronic and thermohydraulic characteristics of a new breeding thorium–uranium mixed SCWR fuel assembly

Shichang Liu, Jiejin Cai · Annals of Nuclear Energy · 2013 · 20 citations

Engineering, Nuclear Engineering, Physics +12