Liangzhi Cao
0000-0002-2872-011X
63 papers found
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Development and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas
A study of the impact of mixed mode of fuel salt in plenum on steady-state performance of channel-type molten salt reactor
Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system
Unstructured coarse mesh finite difference method to accelerate k -eigenvalue and fixed source neutron transport calculations
Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core
Accurate resonance calculation method coupling simplified embedded self-shielding method and ultra-fine group method
Accurate resonance absorption calculation for fuel pins with non-uniform intra-pellet temperature profile based on ultra-fine-group slowing-down calculations
Investigation on the heterogeneous resonance integral in the embedded self-shielding method
Acceleration of the exponential function expansion nodal SP3 method by multi-group GMRES algorithm for PWR pin-by-pin calculation
A modified predictor-corrector quasi-static method in NECP-X for reactor transient analysis based on the 2D/1D transport method
Neutronic design study of a small modular IPWR loaded with accident tolerant-fully ceramic micro-encapsulated (AT-FCM) fuel
Newton-Krylov method with nodal coupling coefficient to solve the coupled neutronics/thermal-hydraulics equations in PWR transient analysis
Numerical analysis on the dynamic behaviors of a graphite-moderated molten salt reactor based on MOREL2.0 code
Conceptual core design study of an innovative small transportable lead-bismuth cooled fast reactor (SPARK) for remote power supply
Hybrid MPI-communication for the multi-angular S N parallel sweep on 3-D regular grids
Predicting spatially dependent reaction rate for problem with nonuniform temperature distribution by subgroup method
Geometry pretreatment method for the 3D modular characteristic method based on AutoCAD
Development and validation of a PWR on-line power-distribution monitoring system NECP-ONION
Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code
On the improvements in neutronics analysis of the unit cell for the pebble-bed fluoride-salt-cooled high-temperature reactor
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