Jingang Liang

New strategies of sensitivity analysis capabilities in continuous-energy Monte Carlo code RMC

Development of random geometry capability in RMC code for stochastic media analysis

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

Computing eigenvalue sensitivity coefficients to nuclear data by adjoint superhistory method and adjoint Wielandt method implemented in RMC code

RMC - A Monte Carlo code for reactor physics analysis

Depletion benchmarks calculation of random media using explicit modeling approach of RMC

Domain Decomposition Strategy for Pin-wise Full-Core Monte Carlo Depletion Calculation with the Reactor Monte Carlo Code

Computing eigenvalue sensitivity coefficients to nuclear data based on the CLUTCH method with RMC code

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

Quantifying Transient Uncertainty in the BEAVRS Benchmark Using Time Series Analysis Methods