affiliation not provided to SSRN
Burnup chain compression method, Generalized perturbation theory, Decay photon source term calculation, Decay heat calculation
Uncertainty quantification, Continuous-energy covariance, Sensitivity analysis, SVD, Monte Carlo
Neutron transport, P1 theory, pin-cell homogenization, PWR-core neutronics calculation, two-step procedur
Data assimilation, Burnup distribution, Three-dimensional variational algorithm, Artificial neutral network algorithm
fast reactor, multigroup cross sections, core calculation
Neutron noise, Monte Carlo Iterative K-source, Frequency Domain Neutron Noise
TBR, SDDR, Monte Carlo, CFETR, NECP-MCX
Delayed photon；Photon heating；Monte Carlo method, Fast reactor
Sensitivity Analysis, IFP, CLUTCH, force collision, Monte Carlo
Resonance elastic scattering, Multi-group cross section, Scattering matrix, NECP-Atlas
Plate-type fuel, strong absorber, fine-mesh homogenization, anisotropic SP3, MTR, JRR-3M
PWR, NECP-Bamboo, validation, AP1000, HPR1000, M310
Chinese Fusion Engineering Test Reactor (CFETR), blanket design, mixed bed breeder, neutronics, Thermal-Hydraulics
Accelerator-Driven Sub-critical system, SARAX code, high-energy neutron database
group condensation, dispersed-particle fuel, double heterogeneity
microreactor, uranium-zirconium hydride fuel, hydrogen kinetics, hydrogen redistribution, hydrogen permeation loss, multiphysics coupling
Uncertainty Analysis, Criticality Safety Analysis, Spent Nuclear Fuel storage
