OOIR: Observatory of International Research

Papers

(The H4-Index of Annals of Nuclear Energy is 28. 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 2021-02-01 to 2025-02-01.)

Article	Citations
An innovative method for building the model of oxidation resistance of Cr coatings	106
Mechanism research of two-phase flow regimes during bottom reflooding in narrow rectangular channel	99
Influence of crust formation on the heat load to a reactor vessel under an in-vessel retention condition	53
Neutronics/thermal-hydraulics/fuel-performance coupling for light water reactors and its application to accident tolerant fuel	49
Experimental measurements to evaluate the effects of fuel microstructure on fission gas release in thoria	47
Experimental study on the influence of inclination on operating characteristics of secondary side passive residual heat removal system	46
The development of fuel management code TRACS for HFETR based on Unstructured-mesh variational nodal method	44
Heat transfer system design of sodium test facility STELLA-2	44
Implementation and testing of unscented transformation and low rank approximation to enhance SCALE code uncertainty calculations	41
Operator actions evaluation for MSGTR accident mitigation	40
Multi-generation point kinetics for subcritical systems	38
Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation	36
Nuclides selection method for nuclear reactor shielding based on non-dominated sorting	36
An application of sensitivity and representativity approach for the design of a 100%MOX BWR experimental program in ZPR	35
Characteristics of liquid film rupture at wave plate corner: A short communication	34
A new sampling scheme combining maximum entropy and moment matching techniques for reactor physics uncertainty quantification	34
A physics-based parametric regression approach for feedwater pump system diagnosis	34
Operation and safety analysis of space lithium-cooled fast nuclear reactor	34
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	32
Source extrapolation scheme for Monte Carlo fission source convergence based on RMC code	32
Evaluation of probabilistic safety margin of nuclear power plant based on optimized adaptive sampling method	31
VVER-1000/V446 spent fuel pool risk assessment and support through portable mitigating equipment	30
Analysis of the Power and Temperature distribution in molten salt reactors with TRACE. Application to the MSRE	29
Evaluation of power distribution calculation of the very high temperature reactor critical assembly (VHTRC) with Monte Carlo MVP3 code	29
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	29

Evaluation of existing correlations and development of a new correlation for single-phase friction factor in rod bundle assembly	28
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	28
Impact of the extended computational domain at inlet and outlet on natural convection in a vertical rectangular channel	28
The gamma deposition matrix method for gamma heating calculations for LWRs	28