OOIR: Observatory of International Research

Papers

(The H4-Index of Nuclear Engineering and Technology is 34. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-04-01 to 2025-04-01.)

Article	Citations
Beyond design basis seismic evaluation of underground liquid storage tanks in existing nuclear power plants using simple method	198
A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations	180
Nuclear power utilization as a future alternative energy on icebreakers	142
Investigation on the thermal characteristics of electronic system and prediction of chip temperature by machine learning	110
A study on the applicability of simplified few-group GET (Generalized Equivalence Theory) to cylindrical molten salt fast reactor	94
Fission accelerated steady-state post irradiation examinations - Part II	90
COFUN: A new tool for evaluating containment failure frequency and uncertainty	89
Influence of dissolved hydrogen and IG Cr carbide on the oxidation behavior of Alloy 600 in hydrogenated primary water	79
CFD analysis of the flow blockage in a rectangular fuel assembly of the IAEA 10 MW MTR research reactor	63
Thermal-hydraulic phenomena and heat removal performance of a passive containment cooling system according to exit loss coefficient	61
Fabrication, characterization, simulation and experimental studies of the ordinary concrete reinforced with micro and nano lead oxide particles against gamma radiation	58
Pump availability prediction using response surface method in nuclear plant	56
Photon dose response functions for accurate skeletal dosimetry for Korean and Asian populations	55
Investigation of neural network-based cathode potential monitoring to support nuclear safeguards of electrorefining in pyroprocessing	55
Development of probabilistic primary water stress corrosion cracking initiation model for alloy 182 welds considering thermal aging and cold work effects	51
Numerical investigation of two-component single-phase natural convection and thermal stratification phenomena in a rod bundle with axial heat flux profile	49
Evaluation of tritium production capability of the 5 MWe gas-cooled graphite-moderated reactor at Yongbyon using tritium-producing burnable absorber rods	48
Differentiated influences of perceived benefit types of nuclear power on its acceptance: Evidence from South Korea	46
Coupled heat and mass transfer simulation of CRUD migration and deposition in PWR systems	44
Analysis of Naturally Occurring Radioactive Material (NORM) in shifting earth layers in Piyungan, Bantul	44
Radioactive gas diffusion simulation and inhaled effective dose evaluation during nuclear decommissioning	43
Graded approach to determine the frequency and difficulty of safety culture attributes: The F-D matrix	42
Design and optimization of thermal neutron activation device based on 5 MeV electron linear accelerator	40
Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor	40
Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code	39

SEM-based study on the impact of safety culture on unsafe behaviors in Chinese nuclear power plants	39
Radioisotope identification using sparse representation with dictionary learning approach for an environmental radiation monitoring system	39
Radioactive waste sampling for characterisation - A Bayesian upgrade	38
Validation of the correlation-based aerosol model in the ISFRA sodium-cooled fast reactor safety analysis code	37
Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code	37
Discrimination of dicentric chromosome from radiation exposure patient data using a pretrained deep learning model	36
Assessment of neutron-induced activation of irradiated samples in a research reactor	35
Investigation of thorium separation from rare-earth extraction residue via electrosorption with carbon based electrode toward reducing waste volume	35
Experimental evaluation of fatigue strength for small diameter socket welded joints under vibration loading condition	35