OOIR: Observatory of International Research

Papers

(The H4-Index of Annals of Nuclear Energy is 31. 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 2022-01-01 to 2026-01-01.)

Article	Citations
Editorial Board	251
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	137
Radiation survey for Taiwan research reactor vessel	71
Impact of experimental effects on a resolved resonance evaluation for practical applications	68
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	59
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	58
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	57
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	56
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	54
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	44
Experimental investigation on sodium leak behaviour through a pinhole	44
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	43
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	42
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	42
A semi-implicit Chord Length Sampling method for dispersion fuel analysis	40
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	39
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	39
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	38
Research on sensor fault tolerance technology in nuclear power plant control system	38
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code	38
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	37
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	36
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	35
Numerical analysis on steam–air condensation at low wall sub-cooling under natural convection	35
Development of lumped-parameter models for debris bed remelting analysis	35

Parametric investigation of mercury cell electrolysis for isotopic separation of Li using coupled numerical methods	34
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	33
Neutron transmission measurements for silica glass at the KURNS-LINAC	32
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	31
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	31
Mapping radioactive environments by use of sparse Gaussian processes regression	31
Verification of depletion capability of OpenMC using VERA depletion benchmark	31
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	31