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 2021-10-01 to 2025-10-01.)

Article	Citations
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	212
Impact of experimental effects on a resolved resonance evaluation for practical applications	129
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	65
The gamma deposition matrix method for gamma heating calculations for LWRs	58
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	58
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	52
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	51
Editorial Board	51
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	45
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	44
Editorial Board	42
An analytic approach to the design of passively safe lead-cooled reactors	41
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	41
Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring	40
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	38
Radiation survey for Taiwan research reactor vessel	38
One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pump	38
Development of lumped-parameter models for debris bed remelting analysis	36
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	36
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	36
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	34
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	34
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	34
Verification of depletion capability of OpenMC using VERA depletion benchmark	32
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	32

Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	31
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	30
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	30
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	30
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	30
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	30
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	30