OOIR: Observatory of International Research

Papers

(The H4-Index of Annals of Nuclear Energy is 33. 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 2022-05-01 to 2026-05-01.)

Article	Citations
Editorial Board	301
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	82
Radiation survey for Taiwan research reactor vessel	76
Impact of experimental effects on a resolved resonance evaluation for practical applications	68
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	64
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code	64
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	63
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	57
Development of lumped-parameter models for debris bed remelting analysis	46
Numerical analysis on steam–air condensation at low wall sub-cooling under natural convection	45
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	45
Neutron transmission measurements for silica glass at the KURNS-LINAC	44
The measurement of the 86Kr(n,2n)85mKr reaction cross section for the d-T neutrons	44
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	43
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	42
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	42
A molten salt test loop for component and instrumentation testing	42
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	41
Verification of depletion capability of OpenMC using VERA depletion benchmark	41
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	40
Experimental investigation on sodium leak behaviour through a pinhole	39
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	38
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	37
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	36
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	36

Editorial Board	36
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	36
Editorial Board	35
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	35
Modelling of the expansion phase of Sodium fast reactor severe accident	35
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	34
Development and verification of the hexagonal core simulation capability of the NECP-X code	34
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	34
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	33