| A new high-fidelity neutronics code NECP-X |
27 |
| Investigation on flow and breakdown characteristics of water film on vertical corrugated plate wall |
19 |
| Dependence assessment in human reliability analysis using an evidential network approach extended by belief rules and uncertainty measures |
19 |
| Research on fault diagnosis methods for the reactor coolant system of nuclear power plant based on D-S evidence theory |
19 |
| Review of research progress on flow and rupture characteristics of liquid film on corrugated plate wall |
15 |
| Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask |
14 |
| Enhanced thermal conductivity accident tolerant fuels for improved reactor safety - A comprehensive review |
13 |
| Autonomous operation algorithm for safety systems of nuclear power plants by using long-short term memory and function-based hierarchical framework |
11 |
| Framework for fault diagnosis with multi-source sensor nodes in nuclear power plants based on a Bayesian network |
11 |
| Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics |
11 |
| Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings |
11 |
| PIV measurement of cross flow in a rod bundle assisted by telecentric optics and matched index of refraction |
10 |
| Dependence assessment in human reliability analysis based on evidence credibility decay model and IOWA operator |
10 |
| CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor |
10 |
| Feasibility of passive autonomous frequency control operation in a Soluble-Boron-Free small PWR |
9 |
| Elastic-plastic behavior of AP1000 nuclear island structure under mainshock-aftershock sequences |
9 |
| Study on the complete rotational characteristic of coolant pump in the gas-liquid two-phase operating condition |
9 |
| Numerical investigation of the separation performance of full-scale AP1000 steam-water separator |
8 |
| Radial distributions of power and isotopic concentrations in candidate accident tolerant fuel U3Si2 and UO2/U3Si2 fuel pins with FeCrAl cladding |
8 |
| The utilization of thorium in Small Modular Reactors - Part I: Neutronic assessment |
8 |
| PIV measurement of turbulent flow downstream of mixing vane spacer grid in 5x5 rod bundle |
8 |
| Continuous machine learning for abnormality identification to aid condition-based maintenance in nuclear power plant |
8 |
| New kinetic simulation capabilities for TRIPOLI-4 (R) : Methods and applications |
8 |
| Development of a Molten Salt Reactor specific depletion code MODEC |
8 |
| Preliminary coupling of the Thermal/Hydraulic solvers in the Monte Carlo code MCS for practical LWR analysis |
8 |
| Effect of surface modification of silica nanoparticles by silane coupling agent on decontamination foam |
8 |
| Simulation analysis of an open natural circulation for the passive residual heat removal in IPWR |
7 |
| Deep rectifier neural network applied to the accident identification problem in a PWR nuclear power plant |
7 |
| Corrosion resistance of candidate cladding materials for supercritical water reactor |
7 |
| Analysis of a small-scale reactor core with PARCS/Serpent |
7 |
| An investigation on flashing-induced natural circulation instabilities based on RELAP5 code |
7 |
| Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches |
7 |
| Effect of gas pressure and bias potential on oxidation resistance of Cr coatings |
7 |
| On the number of tubes required to study oscillating vortices and frequency spectrums of tube arrays in cross flow |
7 |
| U3Si2-SiC fuel performance analysis in BISON during normal operation |
7 |
| Comparative study of application of different supervised learning methods in forecasting future states of NPPs operating parameters |
7 |
| Implementation and performance analysis of the massively parallel method of characteristics based on GPU |
7 |
| Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure |
7 |
| False alarm reducing in PCA method for sensor fault detection in a nuclear power plant |
7 |
| A chattering-free sliding mode control strategy for modular high-temperature gas-cooled reactors |
6 |
| Prediction of rod film thickness of vertical upward co-current adiabatic flow in rod bundle |
6 |
| Conceptual design and analysis of a multipurpose micro nuclear reactor power source |
6 |
| Shapley effect application for variance-based sensitivity analysis of the few-group cross-sections |
6 |
| Investigation on the heterogeneous resonance integral in the embedded self-shielding method |
6 |
| Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments |
6 |
| Development of a Bayesian belief network model for software reliability quantification of digital protection systems in nuclear power plants |
6 |
| Implementation and assessment of wall friction models for LWR core analysis |
6 |
| Assessment of different turbulence models on the large scale internal heated water pool natural convection simulation |
6 |
| Specific heat capacity model for compacted bentonite buffer materials |
6 |
| A comparison of curium, neptunium and americium transmutation feasibility |
6 |
