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 2022-08-01 to 2026-08-01.)

Article	Citations
The effect of ambient temperature variation on the spectrometric performance of NaI (Tl) scintillation detector; an experimental study	34
Study on the diffusion behavior of rhenium in CTAB-modified bentonite	17
Calendar of events	16
Calendar of events – issue 6 of KERN	12
Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe_3−xNd_xO₄	11
Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor	11
Thermo-hydraulic characteristics of molten salt NaNO₃–KNO₃ using numerical simulations	10
Preliminary study neutronic design and optimization of a long-life gas-cooled fast reactor with modified CANDLE scheme using OpenMC	8
Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core	8
Improved deconstruction of components in nuclear power plants through deterministic grain arrangement in diamond wire grinding	8
Model of terminal debris bed formation after a CANDU core collapse	8
Evaluation of the optimum safety performance of the nuclear reactor compact grounding system under lightning strikes and ground fault	7
Reliability assessment of equal height difference passive containment cooling system based on the adaptive metamodel-based subset importance sampling method in inverse uncertainty quantification frame	7
Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor	6
Comparative analysis of Geant4 and MACCS for nuclear accident assessment in Saudi Arabia	6
A detection and defense security system design for nuclear waste storage against stealth terrorists attack	6
A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis	6
Application of internal fire probabilistic risk assessment in design optimization for marine SMR	6
Comparative analysis of swelling and porosity evolution in UO₂ fuel via two approaches	5
Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor	5
Advancing the safety design of heat pipe cooled reactors: a case study of lead liquid bath and monolith stainless steel core	4
CFD modelling of flashing flows for nuclear safety analysis: possibilities and challenges	4
Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning	4
Study on the accidents analyses of a single channel for XADS by using MPC-LBE code	4
Water hammer analysis of essential service water system in nuclear power plant	4

Calendar of events	4
Frontmatter	4
Safety behaviour of a material testing reactor using U ₃ Si ₂ fuel during reactivity insertion acc	3
Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM	3
Prediction of LOCA break sizes using LSTM architecture for pressurized water reactors	3
Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme	3
Study of the effect of virtual mass force on two-phase critical flow	3
Frontmatter	3
Calendar of events	3
Assessment of radiological consequences from a hypothetical nuclear reactor accident at a proposed site in Sierra Leone	3
Calendar of events	3
Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia	3
Calendar of events	3
Heat transfer enhancement of heat exchanger using rectangular channel with cavities	3
Frontmatter	3
The failure probability calculation of the passive system EPS in HPR1000 under LBLOCA based on the importance sampling algorithm	3
Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant	3
Analysis of neutronic performance of VVER 1200 reactor using accident tolerant fuel	3
Development of a sampling system including quality assured sampling procedure for nonaccessible area (Bero)	2
A review on optimal UPFC device placement in electric power systems	2
Calendar of events	2
Heat transfer and pressure drop analysis of a microchannel heat sink using nanofluids for energy applications	2
Economics, supply chain and advanced tolerance fuel requirement of very small modular reactors (vSMR): a case study for Saudi Arabia	2
Calendar of events	2
Study on comprehensive evaluation method of mental workload level	2
A sustainable solution to ensure the dependently and safety of electrical grid relying on optimal allocation of UPFC for research reactor	2
Lithium–lithium fusion evaporation research	2
Neutronic analysis of a lithium-cooled space nuclear reactor based on sliding reflector design	2
Frontmatter	2
Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository	2
Core design and neutronics analysis of lead liquid metal-based heat pipe cooled reactor for undersea purpose	2
Applying multiple processes nonequilibrium model to investigate cesium transport in crushed granite	2
A critique of Canadian regulatory documents for tritium emissions from NPPs	2
Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor	2
Development of a Compton camera supporting the decommissioning of nuclear facilities with advanced radiological measurements	2
Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase	2
Effect of glass cooling method on thermal shock behavior of nuclear waste container	2
Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach	2
Calendar of events	2
Frontmatter	2
Multi-channel GOTHIC model of a postulated spent fuel pool leakage accident for the Maanshan PWR units	1
Participatory development and mixed-methods evaluation of immersive VR training for radiation protection and nuclear safeguards – KISS	1
Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA	1
Frontmatter	1
Preliminary neutronic analyses for annular VHTR with different coated fuel particle designs	1
Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components	1
Study on flow field characteristics of regulator in uranium enrichment centrifugal cascade	1
Frontmatter	1
Frontmatter	1
Investigations into the development of a new type of internal pipe cutting device for difficult to access pipelines	1

Calendar of events	1
Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research	1
One new fuel breeding configuration for long cycle life fast spectrum reactors	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
Brittle failure analysis and modeling of high-burnup PWR fuel cladding alloys	1
Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation	1
Visualization of trouble spots for decontamination work and decision measurements with the help of BIM	1
Comparative neutronic and radiotoxicity analysis of advanced nuclear fuels in a KLT-40S assembly	1
Events	1
Calendar of events	1
15-15Ti cladding behavior during a RIA type event in TRIGA reactor	1
Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water	1
Coupled analysis of ocean-atmosphere interaction using A2CDOSE and SCHISM for radioactive dispersion following a north pacific nuclear incident	1
Improving of electric network feeding nuclear facility based on multiple types DGs placement	1
The RADTRAD and MicroShield analysis methodology for the LOCA during the long-term shutdown period of Chinshan BWR/4 nuclear power plant	1
Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor	1
Role of impurity and thermal noise on the radiation sources in ITER using DT fuel	1
Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm	1
Safety, and security monitoring system for spent nuclear fuel dry cask storage	1
Preliminary analysis of typical accidents of CFETR helium-cooled solid breeder blanket system based on COSINE	1
Evaluating the seismic out-of-plane capacity of unreinforced masonry walls: effects of cantilevered masses	1
Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment	1
Frontmatter	1
Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants	1
A non-dominated discrete differential evolution for fuel loading pattern optimization of a nuclear research reactor	1
GRS contributions to flow-induced vibrations related activities in Europe	1
Signal-based detection of arc phenomena in underwater electrothermal cutting with CAMG for the decommissioning of nuclear facilities	1
Passive safety systems and heat pipe applications in nuclear power plants	1
Calendar of events	1
Severe accident simulation of Kuosheng NPP in reactor shutdown mode with MAAP5	1
Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump	1
New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV	1
Accurate departure from nucleate boiling ratio (DNBR) prediction using SIMCA’s partial least squares regression and clustering	1