OOIR: Observatory of International Research

Papers

(The H4-Index of Annals of Nuclear Energy is 30. 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 2020-04-01 to 2024-04-01.)

Article	Citations
Recent progress of CFD applications in PWR thermal hydraulics study and future directions	137
Py-MLBUF: Development of an online-platform for gamma-ray shielding calculations and investigations	67
Technological solutions for long-term storage of partially used nuclear waste: A critical review	67
Molten salt for advanced energy applications: A review	63
Heat pipe failure accident analysis in megawatt heat pipe cooled reactor	54
Two decades on human reliability analysis: A bibliometric analysis and literature review	44
Improved PCA model for multiple fault detection, isolation and reconstruction of sensors in nuclear power plant	42
Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review	42
Fault identification and diagnosis based on KPCA and similarity clustering for nuclear power plants	42
MCS – A Monte Carlo particle transport code for large-scale power reactor analysis	41
Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor	41
Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods	40
Review of thermophysical property methods applied to fueled and un-fueled molten salts	40
A fuzzy-PID composite controller for core power control of liquid molten salt reactor	38
NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems	37
Advanced fault diagnosis method for nuclear power plant based on convolutional gated recurrent network and enhanced particle swarm optimization	36
Progress in studying the fretting wear/corrosion of nuclear steam generator tubes	36
Uncertainty quantification and software risk analysis for digital twins in the nearly autonomous management and control systems: A review	35
Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%	34
Cold spray technology in nuclear energy applications: A review of recent advances	34
A data-driven adaptive fault diagnosis methodology for nuclear power systems based on NSGAII-CNN	34
Second law analysis of a 3D magnetic buoyancy-driven flow of hybrid nanofluid inside a wavy cubical cavity partially filled with porous layer and non-Newtonian layer	33
Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly	33
Diagnosis of operational failures and on-demand failures in nuclear power plants: An approach based on dynamic Bayesian networks	32
Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system	32

Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors	32
Investigation on effects of Fluid-Structure-Interaction (FSI) on the lubrication performances of water lubricated bearing in primary circuit loop system of nuclear power plant	31
A high-order and efficient numerical technique for the nonlocal neutron diffusion equation representing neutron transport in a nuclear reactor	31
Implementation of Grey Wolf Optimization (GWO) algorithm to multi-objective loading pattern optimization of a PWR reactor	30
A digital twin approach to system-level fault detection and diagnosis for improved equipment health monitoring	30
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	30