OOIR: Observatory of International Research

Papers

(The TQCC of Kerntechnik is 1. 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 2020-11-01 to 2024-11-01.)

Article	Citations
Heat transfer and pressure drop analysis of a microchannel heat sink using nanofluids for energy applications	26
Radioactive waste treatment technology: a review	16
Experimental investigation on pool boiling for downward facing heating with different concentrations of Al₂O₃ nanofluids	9
Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers	8
Half-space albedo problem for the Anlı-Güngör scattering function	8
Preliminary study on TRU transmutation in VVER-1000 fuel assembly using MCNP6	7
Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)	7
A decision-making method based on Bayesian optimization algorithm for small modular reactor	7
Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method	6
Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning	6
Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network	6
Effects of some level density models and γ-ray strength functions on production cross-section calculations of ^16,18O and ^24,26Mg radioisotopes	6
High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO₄) minerals	6
Automatic sentiment analysis of public opinion on nuclear energy	5
Drones application scenarios in a nuclear or radiological emergency	5
Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research	5
Pool boiling performance of oxide nanofluid on a downward-facing heating surface	5
Untraditional solution for enhancing the performance of U-20 % Zr metallic alloy as an ATF using liquid metal bonded gap	5
The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface	4
Dynamic fault tree analysis of auxiliary feedwater system in a pressurized water reactor	4
Application research on neutron-gamma discrimination based on BC501A liquid scintillator	4
Corrosion surveillance program for tank, fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor	4
Experimental investigation of heat transfer characteristics of inclined aluminium two phase closed thermosyphon	3
Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications	3
Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA	3

A sustainable solution to ensure the dependently and safety of electrical grid relying on optimal allocation of UPFC for research reactor	3
Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)	3
An artificial neural network-based numerical estimation of the boiling pressure drop of different refrigerants flowing in smooth and micro-fin tubes	3
Criticality analysis for safety-critical software in nuclear power plant distributed control system	3
A review on optimal UPFC device placement in electric power systems	3
Numerical simulation of the effect of rod bowing on critical heat flux	3
Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers	3
Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor	3
Effectiveness assessment of improvement measures in physical protection system monitoring center	2
Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation	2
An investigation of multistream plate-fin heat exchanger modelling and design: a review	2
Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production	2
Neutronics and both analytical and numerical solutions for the rod centered subchannel thermal-hydraulic model	2
Determination of limiter design and material composition of MT-II spherical tokamak	2
Evaluation of human factor engineering influence in nuclear safety using probabilistic safety assessment techniques	2
Study on specific heat capacity and thermal conductivity of uranium nitride	2
Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology	2
Heat transfer enhancement of heat exchanger using rectangular channel with cavities	2
Review and outlook of the integral test facility PKL III corresponding studies	2
New flow boiling frictional pressure drop multipliers for smooth and microfin tubes	2
Investigation of level density parameter dependence for some ²³³U, ²³⁵U, ²³⁷U, ²³⁹U, ²⁴⁹Cf, ²⁵¹Cf, ²³⁷Pu and ²⁴⁷	2
Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC	2
Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer	2
Editorial	2
Advances in triple tube heat exchangers regarding heat transfer characteristics of single and two-phase flows in comparison to double tube heat exchangers part 1	2
Summary of 3^rd Sino-German symposium on fundamentals of advanced nuclear safety technology	1
Design and optimization of molten salt reactor monitoring system based on digital twin technology	1
Research on the application of ²²Na radiolocation detection technology in advanced manufacturing process control	1
Study of PWR hot leg creep rupture and RCS depressurization strategy during an SBO accident	1
Photon dosimetry using selective data sampling with Particle Swarm optimization algorithm based on NaI(Tl) scintillation detector	1
GRS contributions to flow-induced vibrations related activities in Europe	1
Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor	1
Research reactor model for isotope production based on the design of VVER-440 reactors	1
Optimal operation strategy of LWR based on the PCI online prognosis model	1
An enhanced formalism for the inverse reactor kinetics problem	1
Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM	1
CFD simulation on flow boiling in full scale 5 × 5 rod bundle	1
New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV	1
Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system	1
One-dimensional and three-dimensional coupling simulation research of centrifugal cascade hydraulics	1
Severe accident simulation for VVER-1000 reactor using ASTEC-V2.1.1.3	1
The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows	1
The CANDLE burnup strategy applied to small modular pressurized water reactor loading with fully ceramic microencapsulated fuel	1
Effect of gap design pressure on the LWR fuel rods lifetime	1
Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor	1
Heat transfer characterization under radial jet and falling film induced rewetting	1
Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger	1
²⁴⁴Cm contributions to the alpha source term of CANDU reactors	1
The European GO-VIKING project on flow-induced vibrations: overview and current status	1
Advances in triple tube heat exchangers regarding heat transfer characteristics of single and two-phase flows in comparison to double tube heat exchangers part 2	1

Coupling MCNP6/ANSYS codes to calculate axial temperature and power distribution in a VVER-1000 fuel assembly	1
Probing ⁶He induced reactions with nuclear level density	1
Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition	1
Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors	1
Higher order T_N approximation for the neutron diffusion problem in a slab reactor	1
Investigating the in-core ⁶⁰Co production assembly for open pool type reactor	1
CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle	1
Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO₂, MOX and (Th/U)O₂ using OpenMC	1
Evaluation of the optimum safety performance of the nuclear reactor compact grounding system under lightning strikes and ground fault	1
Lithium–lithium fusion evaporation research	1
Experimental investigation on buffer/backfill materials for radioactive waste repository downward facing sorption additivity of cesium, strontium and cobalt with different concentrations	1
Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia	1
Safety analysis for integrity enhancement in nuclear power plants (NPPs) in case of seashore region site	1
Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code	1
Experimental and theoretical investigation of forced convection heat transfer with CNTs and CuO water based nano-fluids	1
CONTENTS	1
Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC	1
Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code	1
Unfiltered air inleakage analysis of the control room envelope of Kuosheng nuclear power plant	1
Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions	1
Optimization of the TiO₂ nanofluid as a coolant in the VVER-1000 nuclear reactor based on the thermal reactivity feedback coefficients via the genetic algorithm	1
Fuel integrity evaluation method for BWR-6 plant Kuosheng during ATWS events	1
Effect of engraved concentric circles on pool boiling of water	1
Computational analysis of nuclear desalination system under various configurations	1
Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor	1
The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition	1