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 2020-03-01 to 2024-03-01.)

Article	Citations
Investigation of the effects of different composite materials on neutron contamination caused by medical LINAC / Untersuchung der Auswirkungen verschiedener Verbundmaterialien auf die Neutronenkontami	24
Radioactive waste treatment technology: a review	14
Experimental investigation on pool boiling for downward facing heating with different concentrations of Al₂O₃ nanofluids	7
Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers	6
Half-space albedo problem for the Anlı-Güngör scattering function	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
Analysis and evaluation of tomographic gamma scanning image reconstruction algorithm	6
Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)	5
High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO₄) minerals	5
Orifice enabled flow stabilization of natural circulation loop at lower inclinations	5
SKETCH-N/ATHLET steady-state and dynamic coupling scheme verification on Kalinin-3 benchmark results	4
Comparison between standard solid fuel and a new annular fuel performance in the core of a PWR	4
A decision-making method based on Bayesian optimization algorithm for small modular reactor	4
Preliminary study on TRU transmutation in VVER-1000 fuel assembly using MCNP6	4
Untraditional solution for enhancing the performance of U-20 % Zr metallic alloy as an ATF using liquid metal bonded gap	4
Corrosion surveillance program for tank, fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor	4
Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research	3
Application research on neutron-gamma discrimination based on BC501A liquid scintillator	3
Drones application scenarios in a nuclear or radiological emergency	3
Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage	3
Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method	3
A review on optimal UPFC device placement in electric power systems	3
Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)	3
Simulations for L-STAR experimental gas-cooled system / CFD-Nachrechnung von L-STAR-Versuchen zur Wärmeübertragung von turbulenten Gasströmungen	2
FMEA for maintenance criterion at RSG-GAS reactor implemented on JE01-AP01 primary pump	2

Numerical simulation of the effect of rod bowing on critical heat flux	2
Editorial	2
Review and outlook of the integral test facility PKL III corresponding studies	2
"Full-Core" VVER-1000 calculation benchmark	2
Evaluation of human factor engineering influence in nuclear safety using probabilistic safety assessment techniques	2
SEDS benchmark for fuel rod behaviour during dry storage – preliminary results	2
Automatic sentiment analysis of public opinion on nuclear energy	2
Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning	2
Finite element solution of the time-dependent SP₃ equations using an implicit integration scheme	2
Determination of limiter design and material composition of MT-II spherical tokamak	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
A segmented γ scanning device and experimental research	2
Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers	2
The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface	2
Pool boiling performance of oxide nanofluid on a downward-facing heating surface	2
Summary of 3^rd Sino-German symposium on fundamentals of advanced nuclear safety technology	1
Solution of the VVER-1000 full core calculation benchmark by the KARATE code system	1
Dynamic fault tree analysis of auxiliary feedwater system in a pressurized water reactor	1
Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor	1
New flow boiling frictional pressure drop multipliers for smooth and microfin tubes	1
Optimal operation strategy of LWR based on the PCI online prognosis model	1
Experimental and theoretical investigation of forced convection heat transfer with CNTs and CuO water based nano-fluids	1
Validation of new CMS5-VVER nuclear data library using critical experiments and X2 full-core benchmarkjh	1
CFD simulation on flow boiling in full scale 5 × 5 rod bundle	1
Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network	1
Lithium–lithium fusion evaporation research	1
Higher order T_N approximation for the neutron diffusion problem in a slab reactor	1
Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia	1
Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor	1
GRS contributions to flow-induced vibrations related activities in Europe	1
Severe accident simulation for VVER-1000 reactor using ASTEC-V2.1.1.3	1
Heat transfer characterization under radial jet and falling film induced rewetting	1
Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor	1
Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor	1
Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code	1
The CANDLE burnup strategy applied to small modular pressurized water reactor loading with fully ceramic microencapsulated fuel	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
Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications	1
Research reactor model for isotope production based on the design of VVER-440 reactors	1
Coupling MCNP6/ANSYS codes to calculate axial temperature and power distribution in a VVER-1000 fuel assembly	1
Investigation of the temporal rearrangement of zirconium hydride precipitates in cladding material for the interim and final storage period	1
New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV	1
Fuel integrity evaluation method for BWR-6 plant Kuosheng during ATWS events	1
²⁴⁴Cm contributions to the alpha source term of CANDU reactors	1
Computational analysis of nuclear desalination system under various configurations	1
Effect of gap design pressure on the LWR fuel rods lifetime	1
Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO₂, MOX and (Th/U)O₂ using OpenMC	1
Effectiveness assessment of improvement measures in physical protection system monitoring center	1

Neutronics and both analytical and numerical solutions for the rod centered subchannel thermal-hydraulic model	1
Results of the ATHLET/BIPR-VVER software system (version 1.0) certification / Ergebnisse der Zertifizierung des Softwaresystems ATHLET/ BIPR-VVER (Version 1.0)	1
Experimental investigation on buffer/backfill materials for radioactive waste repository downward facing sorption additivity of cesium, strontium and cobalt with different concentrations	1
Fuel cycle of light water reactor with full consumption of recycled uranium	1
Analysis of the startup physics tests of a VVER-1200 reactor with the KARATE- 1200 code system	1
Research on the application of ²²Na radiolocation detection technology in advanced manufacturing process control	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
A sustainable solution to ensure the dependently and safety of electrical grid relying on optimal allocation of UPFC for research reactor	1
Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology	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
Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer	1
Heat transfer enhancement of heat exchanger using rectangular channel with cavities	1
Appraisal of new density coefficient on integrated-nanoparticles concrete in nuclear protection	1
Design and optimization of molten salt reactor monitoring system based on digital twin technology	1
CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle	1
Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation	1
The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition	1
Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA	1
CONTENTS	1
Criticality analysis for safety-critical software in nuclear power plant distributed control system	1