OOIR: Observatory of International Research

Papers

(The H4-Index of Annals of Nuclear Energy is 32. 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 2021-09-01 to 2025-09-01.)

Article	Citations
Modelling of the expansion phase of Sodium fast reactor severe accident	197
Assessment of WWER 1000 core degradation in a severe accident condition induced by MB-LOCA	126
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	68
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR	58
Impact of experimental effects on a resolved resonance evaluation for practical applications	58
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	57
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	56
The gamma deposition matrix method for gamma heating calculations for LWRs	51
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	50
Editorial Board	49
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	48
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	47
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	43
Editorial Board	42
Radiation survey for Taiwan research reactor vessel	41
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	40
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	40
Development of lumped-parameter models for debris bed remelting analysis	38
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	38
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	37
Development and verification of the hexagonal core simulation capability of the NECP-X code	36
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	36
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	36
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	35
Accuracy and efficient solution of helical coiled once-through steam generator model using JFNK method	35

Verification of depletion capability of OpenMC using VERA depletion benchmark	34
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	34
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	34
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	33
Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems	32
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	32
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	32