OOIR: Observatory of International Research

Papers

(The H4-Index of Nuclear Engineering and Technology is 35. 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 2021-11-01 to 2025-11-01.)

Article	Citations
Abnormal detection in nuclear security videos based on label-specific autoencoders and reconstruction errors comparison	231
COFUN: A new tool for evaluating containment failure frequency and uncertainty	159
Analysis of Naturally Occurring Radioactive Material (NORM) in shifting earth layers in Piyungan, Bantul	102
A PHITS based-computational model of a TRIGA-fueled subcritical reactor for gamma dose mapping	99
Study on producing radioisotopes based on fission or radiative capture method in a high flux reactor	87
Experiment of proof-of-principle on prompt gamma-positron emission tomography (PG-PET) system for in-vivo dose distribution verification in proton therapy	75
Study on the cantilever ratio optimization of high-temperature molten salt pump for molten salt reactor based on structural integrity	68
GEOUNED: A new conversion tool from CAD to Monte Carlo geometry	68
Numerical study on the gaseous radioactive pollutant dispersion in urban area from the upstream wind: Impact of the urban morphology	63
CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment	62
Impacts of halloysite clay nanoparticles on the structural and γ-ray shielding properties of the epoxy resin	58
Seismic behavior of simplified electrical cabinet model considering cast-in-place anchor in uncracked and cracked concretes	52
High temperature mechanical properties of diffusion welded alloy 800H	51
A hybrid approach of partially applying BDD for seismic PSA quantification	51
Comparative evaluation of hydrogen production with various chlorine thermochemical cycles integrated in a PACER fusion driver thorium based molten salt reactor	50
An improved CREAM model based on Deng entropy and evidence distance	49
Capabilities of simple calculation models for the analysis of power reactors	49
Theoretical prediction of electronic, mechanical, and thermodynamic properties of layered ternary compounds (UC)nM3C2 (M=Si or Al; n=1,2) and two-dimensional U2C	48
Investigation of the effect of boric acid concentration on neutron reflection coefficient	48
A counting-time optimization method for artificial neural network (ANN) based gamma-ray spectroscopy	46
Balancing the nuclear equation: Climate policy uncertainty and budgetary dynamics	46
SAMG-based human reliability analysis method in support of Level 2 PSA. Part I: Table-top eXercise experiments	44
Monte Carlo-based identification of electron and proton edges for calibration of miniaturized tissue equivalent proportional counter	43
Numerical investigation on mixed convection in narrow rectangular channel under inclination condition	41
Image restoration of underwater fuel assembly thermal turbulence based on improved U-Net network	40

Experimental investigation on effect of ion cyclotron resonance heating on density fluctuation in SOL at EAST	39
Experimental research on flow regime and transitional criterion of slug to churn-turbulent and churn-turbulent to annular flow in rectangular channels	39
Experiment investigation on flow characteristics of open natural circulation system	38
Application of a deep learning algorithm to Compton imaging of radioactive point sources with a single planar CdTe pixelated detector	38
Seismic demand estimation of electrical cabinet in nuclear power plant considering equipment-anchor-interaction	37
Possibility of curium as a fuel for VVER-1200 reactor	37
Dependence assessment in human reliability analysis under uncertain and dynamic situations	36
Development of a dose estimation code for BNCT with GPU accelerated Monte Carlo and collapsed cone Convolution method	36
Role of modifiers on the structural, mechanical, optical and radiation protection attributes of Eu3+ incorporated multi constituent glasses	36
Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code	35