Kerntechnik

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 2021-08-01 to 2025-08-01.)
ArticleCitations
The effect of ambient temperature variation on the spectrometric performance of NaI (Tl) scintillation detector; an experimental study31
Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions23
Calendar of events13
Pool boiling performance of oxide nanofluid on a downward-facing heating surface10
Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−x Nd x O4 9
Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor9
Thermo-hydraulic characteristics of molten salt NaNO3–KNO3 using numerical simulations9
Calendar of events – issue 6 of KERN9
Large eddy fire simulation applications from nuclear industry8
Model of terminal debris bed formation after a CANDU core collapse7
Criticality analysis for safety-critical software in nuclear power plant distributed control system7
Study on the diffusion behavior of rhenium in CTAB-modified bentonite7
Evaluation of the optimum safety performance of the nuclear reactor compact grounding system under lightning strikes and ground fault7
Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor7
Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core7
Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor6
A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis6
Application of internal fire probabilistic risk assessment in design optimization for marine SMR6
Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers5
A detection and defense security system design for nuclear waste storage against stealth terrorists attack5
Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches5
Review and outlook of the integral test facility PKL III corresponding studies5
The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses5
Advancing the safety design of heat pipe cooled reactors: a case study of lead liquid bath and monolith stainless steel core5
Calendar of events4
Numerical simulation of the effect of rod bowing on critical heat flux4
Study on the accidents analyses of a single channel for XADS by using MPC-LBE code4
Frontmatter4
Heat transfer enhancement of heat exchanger using rectangular channel with cavities4
Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning4
CFD modelling of flashing flows for nuclear safety analysis: possibilities and challenges4
Calendar of events3
Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)3
Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme3
A review on optimal UPFC device placement in electric power systems3
An application research for near-surface repository of strontium-90 sorption kinetic model on mudrocks3
Study on comprehensive evaluation method of mental workload level3
Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant3
Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)3
Calendar of events3
Lithium–lithium fusion evaporation research3
A sustainable solution to ensure the dependently and safety of electrical grid relying on optimal allocation of UPFC for research reactor3
Frontmatter3
Study of the effect of virtual mass force on two-phase critical flow3
Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia3
Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM3
Calendar of events3
Calendar of events3
Applying multiple processes nonequilibrium model to investigate cesium transport in crushed granite3
Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor3
Economics, supply chain and advanced tolerance fuel requirement of very small modular reactors (vSMR): a case study for Saudi Arabia2
The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning2
Calendar of events2
Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase2
Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach2
The RADTRAD and MicroShield analysis methodology for the LOCA during the long-term shutdown period of Chinshan BWR/4 nuclear power plant2
Effect of glass cooling method on thermal shock behavior of nuclear waste container2
Neutronic analysis of a lithium-cooled space nuclear reactor based on sliding reflector design2
An enhanced formalism for the inverse reactor kinetics problem2
The CANDLE burnup strategy applied to small modular pressurized water reactor loading with fully ceramic microencapsulated fuel2
Core design and neutronics analysis of lead liquid metal-based heat pipe cooled reactor for undersea purpose2
Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository2
Brittle failure analysis and modeling of high-burnup PWR fuel cladding alloys2
New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV2
Frontmatter2
Calendar of events2
Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor2
Accurate departure from nucleate boiling ratio (DNBR) prediction using SIMCA’s partial least squares regression and clustering2
Heat transfer and pressure drop analysis of a microchannel heat sink using nanofluids for energy applications2
Neutronics and both analytical and numerical solutions for the rod centered subchannel thermal-hydraulic model2
Frontmatter1
Calendar of events1
Large-scale PANDA facility – radiation experiments and CFD calculations1
Frontmatter1
Study on flow field characteristics of regulator in uranium enrichment centrifugal cascade1
A Monte Carlo study on burnup treatment in sodium-cooled reactor with Th fuel1
Drones application scenarios in a nuclear or radiological emergency1
Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components1
Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm1
Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor1
Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core1
Computational analysis of nuclear desalination system under various configurations1
GRS contributions to flow-induced vibrations related activities in Europe1
15-15Ti cladding behavior during a RIA type event in TRIGA reactor1
Coupled analysis of ocean-atmosphere interaction using A2CDOSE and SCHISM for radioactive dispersion following a north pacific nuclear incident1
Comparison of modeling methods for the effective diffusivities of IO3 estimated in compacted bentonite using through-diffusion tests under aerobic conditions1
The effect of surfactant concentrations and surface material on heat transfer coefficient in nucleate boiling regime1
Frontmatter1
Events1
Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment1
Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants1
Evaluating the seismic out-of-plane capacity of unreinforced masonry walls: effects of cantilevered masses1
Effect of engraved concentric circles on pool boiling of water1
Frontmatter1
Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code1
A non-dominated discrete differential evolution for fuel loading pattern optimization of a nuclear research reactor1
Calendar of events1
Positron annihilation lifetime spectroscopy of annealed tungsten1
Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor1
Frontmatter1
Frontmatter1
Preliminary analysis of typical accidents of CFETR helium-cooled solid breeder blanket system based on COSINE1
Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water1
Investigations into the development of a new type of internal pipe cutting device for difficult to access pipelines1
Analysis of the anticipated transient without scram (ATWS) initiated by emergency power mode through the full scope simulator1
Study on specific heat capacity and thermal conductivity of uranium nitride1
Preliminary neutronic analyses for annular VHTR with different coated fuel particle designs1
Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading1
Improving of electric network feeding nuclear facility based on multiple types DGs placement1
Role of impurity and thermal noise on the radiation sources in ITER using DT fuel1
Calendar of events1
Calendar of events1
Calendar of events1
Numerical simulation analysis of high-temperature bent sodium heat pipes1
A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management1
Frontmatter1
Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation1
Frontmatter1
Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump1
Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction1
Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA1
Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research1
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