Kerntechnik

Article	Citations
Heat transfer and pressure drop analysis of a microchannel heat sink using nanofluids for energy applications	26
Radioactive waste treatment technology: a review	16
Experimental investigation on pool boiling for downward facing heating with different concentrations of Al2O3 nanofluids	9
Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers	8
Half-space albedo problem for the Anlı-Güngör scattering function	8
Preliminary study on TRU transmutation in VVER-1000 fuel assembly using MCNP6	7
Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)	7
A decision-making method based on Bayesian optimization algorithm for small modular reactor	7
Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method	6
Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning	6
Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network	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
High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals	6
Automatic sentiment analysis of public opinion on nuclear energy	5
Drones application scenarios in a nuclear or radiological emergency	5
Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research	5
Pool boiling performance of oxide nanofluid on a downward-facing heating surface	5
Untraditional solution for enhancing the performance of U-20 % Zr metallic alloy as an ATF using liquid metal bonded gap	5
The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface	4
Dynamic fault tree analysis of auxiliary feedwater system in a pressurized water reactor	4
Application research on neutron-gamma discrimination based on BC501A liquid scintillator	4
Corrosion surveillance program for tank, fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor	4
Experimental investigation of heat transfer characteristics of inclined aluminium two phase closed thermosyphon	3
Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications	3
Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA	3

A sustainable solution to ensure the dependently and safety of electrical grid relying on optimal allocation of UPFC for research reactor	3
Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)	3
An artificial neural network-based numerical estimation of the boiling pressure drop of different refrigerants flowing in smooth and micro-fin tubes	3
Criticality analysis for safety-critical software in nuclear power plant distributed control system	3
A review on optimal UPFC device placement in electric power systems	3
Numerical simulation of the effect of rod bowing on critical heat flux	3
Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers	3
Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor	3
Effectiveness assessment of improvement measures in physical protection system monitoring center	2
Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation	2
An investigation of multistream plate-fin heat exchanger modelling and design: a review	2
Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production	2
Neutronics and both analytical and numerical solutions for the rod centered subchannel thermal-hydraulic model	2
Determination of limiter design and material composition of MT-II spherical tokamak	2
Evaluation of human factor engineering influence in nuclear safety using probabilistic safety assessment techniques	2
Study on specific heat capacity and thermal conductivity of uranium nitride	2
Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology	2
Heat transfer enhancement of heat exchanger using rectangular channel with cavities	2
Review and outlook of the integral test facility PKL III corresponding studies	2
New flow boiling frictional pressure drop multipliers for smooth and microfin tubes	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
Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer	2
Editorial	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
Summary of 3rd Sino-German symposium on fundamentals of advanced nuclear safety technology	1
Research on the application of 22Na radiolocation detection technology in advanced manufacturing process control	1
Photon dosimetry using selective data sampling with Particle Swarm optimization algorithm based on NaI(Tl) scintillation detector	1
Research reactor model for isotope production based on the design of VVER-440 reactors	1
Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor	1
An enhanced formalism for the inverse reactor kinetics problem	1
Effect of gap design pressure on the LWR fuel rods lifetime	1
Optimal operation strategy of LWR based on the PCI online prognosis model	1
Heat transfer characterization under radial jet and falling film induced rewetting	1
CFD simulation on flow boiling in full scale 5 × 5 rod bundle	1
244Cm contributions to the alpha source term of CANDU reactors	1
New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV	1
Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition	1
Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system	1
One-dimensional and three-dimensional coupling simulation research of centrifugal cascade hydraulics	1
Severe accident simulation for VVER-1000 reactor using ASTEC-V2.1.1.3	1
The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows	1
The CANDLE burnup strategy applied to small modular pressurized water reactor loading with fully ceramic microencapsulated fuel	1
Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor	1
Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger	1
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	1
Lithium–lithium fusion evaporation research	1
The European GO-VIKING project on flow-induced vibrations: overview and current status	1
Probing 6He induced reactions with nuclear level density	1
Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia	1

Coupling MCNP6/ANSYS codes to calculate axial temperature and power distribution in a VVER-1000 fuel assembly	1
Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code	1
Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors	1
CONTENTS	1
Higher order TN approximation for the neutron diffusion problem in a slab reactor	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
Investigating the in-core 60Co production assembly for open pool type reactor	1
CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle	1
Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO2, MOX and (Th/U)O2 using OpenMC	1
Evaluation of the optimum safety performance of the nuclear reactor compact grounding system under lightning strikes and ground fault	1
Experimental investigation on buffer/backfill materials for radioactive waste repository downward facing sorption additivity of cesium, strontium and cobalt with different concentrations	1
Safety analysis for integrity enhancement in nuclear power plants (NPPs) in case of seashore region site	1
Experimental and theoretical investigation of forced convection heat transfer with CNTs and CuO water based nano-fluids	1
Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code	1
Design and optimization of molten salt reactor monitoring system based on digital twin technology	1
Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC	1
Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions	1
Study of PWR hot leg creep rupture and RCS depressurization strategy during an SBO accident	1
Unfiltered air inleakage analysis of the control room envelope of Kuosheng nuclear power plant	1
GRS contributions to flow-induced vibrations related activities in Europe	1
Fuel integrity evaluation method for BWR-6 plant Kuosheng during ATWS events	1
Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM	1
Effect of engraved concentric circles on pool boiling of water	1
Computational analysis of nuclear desalination system under various configurations	1
Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor	1
The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition	1
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Study of a perforated hollow cylinder and twisted tape inserts as a compound device in a circular tube for heat transfer enhancement	0
An application research for near-surface repository of strontium-90 sorption kinetic model on mudrocks	0
Comparison of heat transfer in natural and forced circulation under rolling motion	0
Developing a futuristic multi-objective optimization of the fuel management problems for the nuclear research reactors	0
Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)	0
Study on calculation model and risk area of radionuclide diffusion in coastal waters under nuclear leakage accidents with different levels	0
Frontmatter	0
ANSYS-CFX simulation of the SRBTL test loop core with nanofluid coolant	0
Calendar of events	0
A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event	0
Frontmatter	0
Radiation shielding properties of mortars containing heavyweight particles	0
LOCA analysis of BWR-4/Mark-I nuclear power plant with TRACE	0
Frontmatter	0
Methodology of probabilistic safety assessment for transportation of radioactive material	0
Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor	0
Calendar of events	0
Implementation of the preCICE coupling interface for AC2/ATHLET	0
Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository	0
Fuzzy reliability algorithm for the shutdown system of research reactor	0
Impact of control rod insertion during burnup on PWR fuel assembly isotopic composition	0
Numerical simulation analysis of high-temperature bent sodium heat pipes	0
A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials	0
Overview on GRS CFD activities related to containment applications	0
Calendar of events	0
Model of terminal debris bed formation after a CANDU core collapse	0
Calendar of events	0
Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation	0
Experimental study on boiling heat transfer of γ-Fe2O3 nanofluids on a downward heated surface	0
Simulation of turbulent mixing rate in simulated subchannels of a reactor rod bundle	0
Comparison of modeling methods for the effective diffusivities of IO3 − estimated in compacted bentonite using through-diffusion tests under aerobic conditions	0
A non-dominated discrete differential evolution for fuel loading pattern optimization of a nuclear research reactor	0
Calendar of events	0
Calendar of events	0
Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators	0
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Discussion of options to increase the control drum worth in fast reactor	0
The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning	0
Effect of metal layer height on heat transfer inside molten pool	0
Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor	0
Analysis of the anticipated transient without scram (ATWS) initiated by emergency power mode through the full scope simulator	0
Improving FNMC for the matrix effect of spherical shell plutonium samples	0
Methodology for analyzing accidents with radioactive material release with code EPZDose	0
A study of RCS depressurization strategy of CPR1000 SAMG	0
Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core	0
Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water	0
Updating risk model for SGTR accident based on success criteria analysis	0
Calendar of events	0
Calendar of events	0
Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE	0
Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach	0

Application of radio analytical tracer technique to study the performance of industrial grade ion exchange resin exposed to UV radiations	0
Large eddy fire simulation applications from nuclear industry	0
Thermal hydraulic analysis of VVER spent fuels stored in vault dry system under different operating and design conditions	0
INHALT	0
Neutronic analysis of the European sodium cooled fast reactor with Monte Carlo code OpenMC	0
Frontmatter	0
Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology	0
Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches	0
Coupled AC2-CFD simulations for a high-pressure core melt accident scenario	0
Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies	0
Temperature adjusted cross section libraries used for criticality calculations	0
Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration	0
The evaluation of TRACE/PARCS model for BWR-4 nuclear power plant by startup test transient analyses	0
Scaling factors for CANDU reactor waste: how reliable are they?	0
State-of-art review of beyond design basis evaluation approach of a generic nuclear power plant in the UK	0
Frontmatter	0
Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction	0
Enhanced heat transfer in corrugated plate fin heat sink	0
Appraisal of new density coefficient on integrated-nanoparticles concrete in nuclear protection	0
Calendar of events	0
Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering	0
Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm	0
CFD simulation on droplet behaviour in post-dryout region	0
A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management	0
Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase	0
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A detection and defense security system design for nuclear waste storage against stealth terrorists attack	0
Calendar of events	0
Study on comprehensive evaluation method of mental workload level	0
CFD modeling of natural convection in pebble bed geometry with finite volume method	0
Note · Imprint	0
Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor	0
CFD and machine learning based hybrid model for passive dilution of helium in a top ventilated compartment	0
Frontmatter	0
The analysis of fire ignition frequency calculation for small modular light water reactors	0
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Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR	0
Transient analysis of MTR research reactor during fast and slow loss of flow accident	0
Calendar of events	0
Frontmatter	0
Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants	0
Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition	0
Frontmatter	0
Methodology for integral analysis of ATWS for Kuosheng nuclear power station	0
CONTENTS	0
Design of an unattended ore grading measurement system in a uranium mine	0
Calendar of events	0
Calendar of events	0
A Monte Carlo study on burnup treatment in sodium-cooled reactor with Th fuel	0
Application of internal fire probabilistic risk assessment in design optimization for marine SMR	0
Development and usage of the digital SAMG system	0
Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading	0
Establishment of analysis methodology for ionizing mattresses using RESRAD-BUILD code	0
Analysis of 4-inch cold leg top-slot break LOCA in ATLAS experimental facility using MARS-KS	0
Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment	0
The 34th German CFD network of competence meeting: numerical 3D simulation of reactor primary cooling circuit and containment flows	0
Effect of using graphene/water based nanofluid on heat transfer in heat exchangers with rotating straight inner tube	0
Study on the accidents analyses of a single channel for XADS by using MPC-LBE code	0
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Large-scale PANDA facility – radiation experiments and CFD calculations	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
Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method	0
Role of impurity and thermal noise on the radiation sources in ITER using DT fuel	0
Establishment of analysis methodology of RADTRAD for Maanshan PWR ATWS	0
Modeling and simulation of deposited energy gain via irradiation of heavy ion beams on the fusion reactor contains spherical fuel capsules with foam	0
Reliability analysis of digital reactor protection systems in floating nuclear power plants	0
Scientific inheritance of Eugenijus Ušpuras	0
Preliminary neutronic analyses for annular VHTR with different coated fuel particle designs	0
Contents	0
CFD modelling of flashing flows for nuclear safety analysis: possibilities and challenges	0
Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor	0
Calendar of events	0
Frontmatter	0
Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code	0
Comparison of back propagation network and radial basis function network in Departure from Nucleate Boiling Ratio (DNBR) calculation	0
Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−x Nd x O4	0
INHALT	0
System theory safety analysis of network malfunction in nuclear power plant distributed control systems	0
Optimization strategy for SAM in nuclear power plants based on NSGA-II	0
Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor	0
A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis	0
Safety of Extended Dry Storage of Spent Nuclear Fuel SEDS2020: International online-workshop	0
Calculation studies of coated particles performance in sodium-cooled fast reactor	0
Positron annihilation lifetime spectroscopy of annealed tungsten	0
Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis	0
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Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu an	0
Determination of heat flux leading to the onset of flow instability in MTR reactors	0
Calendar of events	0
Calendar of events	0
Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage	0
Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor	0
Pressurizer system dynamic model for transient control in PWR	0
Improving of electric network feeding nuclear facility based on multiple types DGs placement	0
The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses	0