OOIR: Observatory of International Research

Papers

(The H4-Index of Annals of Nuclear Energy is 29. 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 2021-05-01 to 2025-05-01.)

Article	Citations
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	154
A novel approach for software reliability analysis of digital instrumentation and control systems in nuclear power plants	117
Modelling of the expansion phase of Sodium fast reactor severe accident	64
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	55
Assessment of WWER 1000 core degradation in a severe accident condition induced by MB-LOCA	51
Development and verification of the hexagonal core simulation capability of the NECP-X code	50
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code	47
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	44
Impact of experimental effects on a resolved resonance evaluation for practical applications	43
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR	42
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	41
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	41
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	40
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	38
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	36
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	36
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	35
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	34
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	34
Rasterized coarse mesh finite difference acceleration on method of characteristics for a reactor core with a generalized boundary	34
The gamma deposition matrix method for gamma heating calculations for LWRs	33
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	32
A molten salt test loop for component and instrumentation testing	31
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	30
Experimental investigation on sodium leak behaviour through a pinhole	30

Editorial Board	30
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	30
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	29
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	29
Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring	29
Editorial Board	29
Radiation survey for Taiwan research reactor vessel	29
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	29
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	29