Kerntechnik

Article	Citations
A review on optimal UPFC device placement in electric power systems	29
Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method	18
Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions	12
Study on flow field characteristics of regulator in uranium enrichment centrifugal cascade	9
An enhanced formalism for the inverse reactor kinetics problem	8
Methodology for analyzing accidents with radioactive material release with code EPZDose	8
Frontmatter	7
Frontmatter	6
Evaluating the seismic out-of-plane capacity of unreinforced masonry walls: effects of cantilevered masses	6
Determination of limiter design and material composition of MT-II spherical tokamak	6
Large eddy fire simulation applications from nuclear industry	6
Calendar of events	6
An application research for near-surface repository of strontium-90 sorption kinetic model on mudrocks	5
Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition	5
Calendar of events	5
Improving of electric network feeding nuclear facility based on multiple types DGs placement	5
Calendar of events	5
Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−x Nd x O4	4
Probing 6He induced reactions with nuclear level density	4
New flow boiling frictional pressure drop multipliers for smooth and microfin tubes	4
Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor	4
Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code	4
Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor	3
Photon dosimetry using selective data sampling with Particle Swarm optimization algorithm based on NaI(Tl) scintillation detector	3
Calendar of events	3

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	3
Calendar of events	3
Experimental and theoretical investigation of forced convection heat transfer with CNTs and CuO water based nano-fluids	3
Study on comprehensive evaluation method of mental workload level	3
Thermo-hydraulic characteristics of molten salt NaNO3–KNO3 using numerical simulations	3
Positron annihilation lifetime spectroscopy of annealed tungsten	3
Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR	3
Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm	3
Simulation of turbulent mixing rate in simulated subchannels of a reactor rod bundle	3
Corrosion surveillance program for tank, fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor	3
Applying multiple processes nonequilibrium model to investigate cesium transport in crushed granite	3
Pool boiling performance of oxide nanofluid on a downward-facing heating surface	3
The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning	3
Safety analysis for integrity enhancement in nuclear power plants (NPPs) in case of seashore region site	2
A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials	2
Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger	2
Enhanced heat transfer in corrugated plate fin heat sink	2
Preliminary study on TRU transmutation in VVER-1000 fuel assembly using MCNP6	2
A sustainable solution to ensure the dependently and safety of electrical grid relying on optimal allocation of UPFC for research reactor	2
Evaluation of the optimum safety performance of the nuclear reactor compact grounding system under lightning strikes and ground fault	2
Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor	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
Calendar of events – issue 6 of KERN	2
Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor	2
Analysis of the anticipated transient without scram (ATWS) initiated by emergency power mode through the full scope simulator	1
Radioactive waste treatment technology: a review	1
Optimization strategy for SAM in nuclear power plants based on NSGA-II	1
Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase	1
Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach	1
Thermal-hydraulic and safety analysis of alternative ceramic fuels in next generation of VVER-1000 reactor	1
Research on the application of 22Na radiolocation detection technology in advanced manufacturing process control	1
A non-dominated discrete differential evolution for fuel loading pattern optimization of a nuclear research reactor	1
Large-scale PANDA facility – radiation experiments and CFD calculations	1
Heat transfer and pressure drop analysis of a microchannel heat sink using nanofluids for energy applications	1
Development and usage of the digital SAMG system	1
Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering	1
Core design and neutronics analysis of lead liquid metal-based heat pipe cooled reactor for undersea purpose	1
Optimal design of an eddy current sensor for detecting and characterizing cracks by data inversion: parametric study	1
Half-space albedo problem for the Anlı-Güngör scattering function	1
Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor	1
Preliminary neutronic analyses for annular VHTR with different coated fuel particle designs	1
Economics, supply chain and advanced tolerance fuel requirement of very small modular reactors (vSMR): a case study for Saudi Arabia	1
Frontmatter	1
Calculation and application research on real-time source term diffusion in NPP auxiliary building under accident circumstances	1
Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository	1
Numerical simulation analysis of high-temperature bent sodium heat pipes	1
Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment	1
Calendar of events	1
Frontmatter	1
Modeling and simulation of deposited energy gain via irradiation of heavy ion beams on the fusion reactor contains spherical fuel capsules with foam	1

Coupled AC2-CFD simulations for a high-pressure core melt accident scenario	1
The CANDLE burnup strategy applied to small modular pressurized water reactor loading with fully ceramic microencapsulated fuel	1
Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core	1
Frontmatter	1
Design of an unattended ore grading measurement system in a uranium mine	1
Frontmatter	1
Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA	1
The analysis of fire ignition frequency calculation for small modular light water reactors	1
Calendar of events	1
Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu an	1
Study of reliability prediction method and uncertainty analysis of the pump and valve of a floating nuclear power plant	1
Experimental investigation on buffer/backfill materials for radioactive waste repository downward facing sorption additivity of cesium, strontium and cobalt with different concentrations	1
Drones application scenarios in a nuclear or radiological emergency	1
Calendar of events	1
Criticality analysis for safety-critical software in nuclear power plant distributed control system	1
Scaling factors for CANDU reactor waste: how reliable are they?	1
Model of terminal debris bed formation after a CANDU core collapse	1
Neutronic analysis of a lithium-cooled space nuclear reactor based on sliding reflector design	1
Risk analysis and protection in case of intrusion of nuclear facilities	1
Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction	1
Structural mechanics in reactor technology (SMiRT) conference series: 50th anniversary conference	1
Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water	1
The RADTRAD and MicroShield analysis methodology for the LOCA during the long-term shutdown period of Chinshan BWR/4 nuclear power plant	0
Updating risk model for SGTR accident based on success criteria analysis	0
Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code	0
Heat transfer characterization under radial jet and falling film induced rewetting	0
Application of internal fire probabilistic risk assessment in design optimization for marine SMR	0
Application of radio analytical tracer technique to study the performance of industrial grade ion exchange resin exposed to UV radiations	0
A detection and defense security system design for nuclear waste storage against stealth terrorists attack	0
Lithium–lithium fusion evaporation research	0
Frontmatter	0
One-dimensional and three-dimensional coupling simulation research of centrifugal cascade hydraulics	0
Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme	0
Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor	0
Monte Carlo simulation of photo-peak efficiency response function and calculation of total efficiency for a NaI (Tl) scintillator detector	0
Neutronic analysis of the European sodium cooled fast reactor with Monte Carlo code OpenMC	0
Calculation of core neutronic parameters in electron accelerator driven subcritical TRIGA reactor	0
Investigating the in-core 60Co production assembly for open pool type reactor	0
Heat transfer at the step of a CANDU calandria during a severe accident	0
A comprehensive assessment on recent advancements in spent fuel reprocessing and waste management: pioneering technologies for a sustainable nuclear future	0
The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows	0
Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition	0
Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation	0
Effect of gap design pressure on the LWR fuel rods lifetime	0
Events	0
Experimental study on boiling heat transfer of γ-Fe2O3 nanofluids on a downward heated surface	0
Comparison of thermal hydraulic performance between horizontal and vertical steam generators in nuclear power plants	0
Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology	0
Methodology of probabilistic safety assessment for transportation of radioactive material	0
Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers	0
Calendar of events	0
Generic flame extension model development based on machine learning for NPPs fire hazard analysis (FHA)	0
Frontmatter	0
Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code	0
State-of-art review of beyond design basis evaluation approach of a generic nuclear power plant in the UK	0
Calendar of events	0
Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network	0
Unfiltered air inleakage analysis of the control room envelope of Kuosheng nuclear power plant	0
Optimization of divertor design for Pakistan spherical tokamak	0
Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump	0
Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies	0
Application research on neutron-gamma discrimination based on BC501A liquid scintillator	0
Neutronics and both analytical and numerical solutions for the rod centered subchannel thermal-hydraulic model	0
Experimental investigation of heat transfer characteristics of inclined aluminium two phase closed thermosyphon	0
Frontmatter	0
Calendar of events	0
Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core	0
Discussion of options to increase the control drum worth in fast reactor	0
Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system	0
Integrating reliability analysis into MBSE for FPGA-based safety critical I&C system design in nuclear power plants	0
Review and outlook of the integral test facility PKL III corresponding studies	0
Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants	0
Analysis of hypothetical channel flow blockage of a tubular fuel assembly in a 10 MWth nuclear research reactor	0
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	0
Frontmatter	0
Calendar of events	0
CFD modeling of natural convection in pebble bed geometry with finite volume method	0
Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers	0
Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches	0
Automatic sentiment analysis of public opinion on nuclear energy	0

System theory safety analysis of network malfunction in nuclear power plant distributed control systems	0
Analyses of the unavailability dynamics of emergency core cooling system	0
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	0
Frontmatter	0
Ecological interface design and evaluation for feedwater dearating system in NPPs	0
Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO2, MOX and (Th/U)O2 using OpenMC	0
Frontmatter	0
Study of PWR hot leg creep rupture and RCS depressurization strategy during an SBO accident	0
The evaluation of TRACE/PARCS model for BWR-4 nuclear power plant by startup test transient analyses	0
Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments	0
Frontmatter	0
Evaluation of radiation interaction parameters of some shape memory alloys	0
Closed form formulae for two interacting equal parallel through-wall cracks embedded in an infinite elastic medium under normal tension	0
Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor	0
Study on specific heat capacity and thermal conductivity of uranium nitride	0
Coupled analysis of ocean-atmosphere interaction using A2CDOSE and SCHISM for radioactive dispersion following a north pacific nuclear incident	0
Evaluation of human factor engineering influence in nuclear safety using probabilistic safety assessment techniques	0
Frontmatter	0
Severe accident simulation for VVER-1000 reactor using ASTEC-V2.1.1.3	0
The RADTRAD analysis methodology for the Fuel Handling Accident during the long-term shutdown period of Chinshan Nuclear Power Plant	0
Numerical modelling of creep, agin and leakage of the prestressed reinforced concrete structure. Application to concrete containment building	0
Fragility analysis of nuclear steam supply system components of a pressurized water reactor	0
Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components	0
Frontmatter	0
Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC	0
Study of the effect of virtual mass force on two-phase critical flow	0
Neutronic and thermal-hydraulic assessment of the TRR with new core designed based on tubular fuels	0
Transient analyses on overpower transients of small modular natural circulation Lead-cooled fast reactor SNCLFR-100	0
Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs)	0
Effect of engraved concentric circles on pool boiling of water	0
Improving FNMC for the matrix effect of spherical shell plutonium samples	0
Frontmatter	0
Design and optimization of molten salt reactor monitoring system based on digital twin technology	0
Calendar of events	0
Study on spent fuel heatup during spent fuel pool complete loss of coolant accident	0
Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor	0
Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)	0
Calendar of events	0
Computational analysis of nuclear desalination system under various configurations	0
Frontmatter	0
Improved intelligent model predictive controller for the nuclear power reactor system	0
Testing the thermal performance of water cooling towers	0
Brittle failure analysis and modeling of high-burnup PWR fuel cladding alloys	0
Pressurizer system dynamic model for transient control in PWR	0
A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis	0
CTAB modification bentonite for enhanced Re adsorption and diffusion suppression	0
Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE	0
Study of a perforated hollow cylinder and twisted tape inserts as a compound device in a circular tube for heat transfer enhancement	0
Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation	0
Design and optimization of an integrated gamma ray scanning system for the uranium sample	0
Characterization of polystyrene and polyacrylic based polymeric materials exposed to oxidative degradation	0
Comparison of modeling methods for the effective diffusivities of IO3 − estimated in compacted bentonite using through-diffusion tests under aerobic conditions	0
Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant	0
Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage	0
An study on seismic soil-structure interaction (SSI) effects for a base-isolated structure on firm soil	0
Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators	0
Study on the regularity of Se(IV) adsorption by bentonite from different regions	0
Frontmatter	0
Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading	0
An application for nonlinear heterogeneity-based isotherm models in characterization of niobium sorption on clay rocks and granite	0
Implementation of the preCICE coupling interface for AC2/ATHLET	0
Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM	0
Frontmatter	0
Thorium-based CANDU qualification as plutonium burner	0
Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications	0
Untraditional solution for enhancing the performance of U-20 % Zr metallic alloy as an ATF using liquid metal bonded gap	0
Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC	0
15-15Ti cladding behavior during a RIA type event in TRIGA reactor	0
The effect of surfactant concentrations and surface material on heat transfer coefficient in nucleate boiling regime	0
Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops	0
Effects of some level density models and γ-ray strength functions on production cross-section calculations of 16,18O and 24,26Mg radioisotopes	0
Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors	0
A blockchain based scheme for distributed storage of nuclear power plant images	0
An investigation of multistream plate-fin heat exchanger modelling and design: a review	0
Dynamic characteristics tests of full-scale lead rubber bearing (LRB)	0
Numerical simulation of the effect of rod bowing on critical heat flux	0
Calendar of events	0
The European GO-VIKING project on flow-induced vibrations: overview and current status	0
GRS contributions to flow-induced vibrations related activities in Europe	0
Study on calculation model and risk area of radionuclide diffusion in coastal waters under nuclear leakage accidents with different levels	0
Effect of metal layer height on heat transfer inside molten pool	0
Development of new ISO 4917 standard series for the design of nuclear power plants against seismic events	0
A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management	0
The 34th German CFD network of competence meeting: numerical 3D simulation of reactor primary cooling circuit and containment flows	0
An approach for an extension of the deflagration model in containment code system COCOSYS to separate burned and unburned atmosphere via junctions	0
Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia	0
Higher order TN approximation for the neutron diffusion problem in a slab reactor	0
Coupling MCNP6/ANSYS codes to calculate axial temperature and power distribution in a VVER-1000 fuel assembly	0
Calendar of events	0
Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor	0
Investigation of effects of nonavailability of passive safety systems on the reactor behaviour during LOCA Scenario in AP600	0
Frontmatter	0
Determination of heat flux leading to the onset of flow instability in MTR reactors	0
Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor	0
Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor	0