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 2021-09-01 to 2025-09-01.)

Article	Citations
Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions	31
Calendar of events	23
Pool boiling performance of oxide nanofluid on a downward-facing heating surface	13
Calendar of events – issue 6 of KERN	10
Study on the diffusion behavior of rhenium in CTAB-modified bentonite	9
Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor	9
Thermo-hydraulic characteristics of molten salt NaNO₃–KNO₃ using numerical simulations	9
Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe_3−xNd_xO₄	9
The effect of ambient temperature variation on the spectrometric performance of NaI (Tl) scintillation detector; an experimental study	8
Evaluation of the optimum safety performance of the nuclear reactor compact grounding system under lightning strikes and ground fault	7
Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core	7
Criticality analysis for safety-critical software in nuclear power plant distributed control system	7
A detection and defense security system design for nuclear waste storage against stealth terrorists attack	7
Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor	7
Model of terminal debris bed formation after a CANDU core collapse	7
Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor	6
Application of internal fire probabilistic risk assessment in design optimization for marine SMR	6
Review and outlook of the integral test facility PKL III corresponding studies	6
A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis	6
Heat transfer enhancement of heat exchanger using rectangular channel with cavities	5
The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses	5
Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning	5
Comparative analysis of swelling and porosity evolution in UO₂ fuel via two approaches	5
Advancing the safety design of heat pipe cooled reactors: a case study of lead liquid bath and monolith stainless steel core	4
Frontmatter	4

Study on the accidents analyses of a single channel for XADS by using MPC-LBE code	4
Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers	4
Numerical simulation of the effect of rod bowing on critical heat flux	4
Calendar of events	4
Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)	4
CFD modelling of flashing flows for nuclear safety analysis: possibilities and challenges	4
An enhanced formalism for the inverse reactor kinetics problem	3
Study of the effect of virtual mass force on two-phase critical flow	3
Calendar of events	3
Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme	3
Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia	3
A sustainable solution to ensure the dependently and safety of electrical grid relying on optimal allocation of UPFC for research reactor	3
An application research for near-surface repository of strontium-90 sorption kinetic model on mudrocks	3
A review on optimal UPFC device placement in electric power systems	3
Calendar of events	3
Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)	3
Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant	3
Calendar of events	3
Study on comprehensive evaluation method of mental workload level	3
Frontmatter	3
Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM	3
Calendar of events	3
Lithium–lithium fusion evaporation research	3
Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor	3
Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor	2
Applying multiple processes nonequilibrium model to investigate cesium transport in crushed granite	2
Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository	2
Heat transfer and pressure drop analysis of a microchannel heat sink using nanofluids for energy applications	2
Calendar of events	2
Brittle failure analysis and modeling of high-burnup PWR fuel cladding alloys	2
Calendar of events	2
The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning	2
The CANDLE burnup strategy applied to small modular pressurized water reactor loading with fully ceramic microencapsulated fuel	2
Role of impurity and thermal noise on the radiation sources in ITER using DT fuel	2
Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research	2
New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV	2
The RADTRAD and MicroShield analysis methodology for the LOCA during the long-term shutdown period of Chinshan BWR/4 nuclear power plant	2
Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach	2
Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase	2
Core design and neutronics analysis of lead liquid metal-based heat pipe cooled reactor for undersea purpose	2
Economics, supply chain and advanced tolerance fuel requirement of very small modular reactors (vSMR): a case study for Saudi Arabia	2
Neutronic analysis of a lithium-cooled space nuclear reactor based on sliding reflector design	2
Effect of engraved concentric circles on pool boiling of water	2
Accurate departure from nucleate boiling ratio (DNBR) prediction using SIMCA’s partial least squares regression and clustering	2
Effect of glass cooling method on thermal shock behavior of nuclear waste container	2
Calendar of events	2
Calendar of events	1
Transient analysis of MTR research reactor during fast and slow loss of flow accident	1
Computational analysis of nuclear desalination system under various configurations	1
Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation	1

A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management	1
Positron annihilation lifetime spectroscopy of annealed tungsten	1
Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water	1
Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump	1
Analysis of the anticipated transient without scram (ATWS) initiated by emergency power mode through the full scope simulator	1
Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading	1
Preliminary neutronic analyses for annular VHTR with different coated fuel particle designs	1
Coupled analysis of ocean-atmosphere interaction using A2CDOSE and SCHISM for radioactive dispersion following a north pacific nuclear incident	1
Calendar of events	1
Numerical simulation analysis of high-temperature bent sodium heat pipes	1
Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components	1
Frontmatter	1
Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction	1
Study on flow field characteristics of regulator in uranium enrichment centrifugal cascade	1
Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor	1
The effect of surfactant concentrations and surface material on heat transfer coefficient in nucleate boiling regime	1
GRS contributions to flow-induced vibrations related activities in Europe	1
Looking for situation awareness in nuclear power plant: uncovering information requirement and influencing factors through a goal-directed task analysis	1
Calendar of events	1
Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA	1
Preliminary analysis of typical accidents of CFETR helium-cooled solid breeder blanket system based on COSINE	1
Frontmatter	1
Frontmatter	1
A non-dominated discrete differential evolution for fuel loading pattern optimization of a nuclear research reactor	1
Investigations into the development of a new type of internal pipe cutting device for difficult to access pipelines	1
Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants	1
Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm	1
Calendar of events	1
Evaluating the seismic out-of-plane capacity of unreinforced masonry walls: effects of cantilevered masses	1
Improving of electric network feeding nuclear facility based on multiple types DGs placement	1
Frontmatter	1
Frontmatter	1
Comparison of modeling methods for the effective diffusivities of IO₃ ⁻ estimated in compacted bentonite using through-diffusion tests under aerobic conditions	1
Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code	1
Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment	1
Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor	1
Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core	1
15-15Ti cladding behavior during a RIA type event in TRIGA reactor	1
Large-scale PANDA facility – radiation experiments and CFD calculations	1
Frontmatter	1
Drones application scenarios in a nuclear or radiological emergency	1
Frontmatter	1
Study on specific heat capacity and thermal conductivity of uranium nitride	1
Frontmatter	1
Events	1