Kerntechnik

Article	Citations
Investigation of the effects of different composite materials on neutron contamination caused by medical LINAC / Untersuchung der Auswirkungen verschiedener Verbundmaterialien auf die Neutronenkontami	24
Radioactive waste treatment technology: a review	14
Experimental investigation on pool boiling for downward facing heating with different concentrations of Al2O3 nanofluids	7
Analysis and evaluation of tomographic gamma scanning image reconstruction algorithm	6
Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers	6
Half-space albedo problem for the Anlı-Güngör scattering function	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
Orifice enabled flow stabilization of natural circulation loop at lower inclinations	5
Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)	5
High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals	5
Untraditional solution for enhancing the performance of U-20 % Zr metallic alloy as an ATF using liquid metal bonded gap	4
Corrosion surveillance program for tank, fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor	4
SKETCH-N/ATHLET steady-state and dynamic coupling scheme verification on Kalinin-3 benchmark results	4
Comparison between standard solid fuel and a new annular fuel performance in the core of a PWR	4
A decision-making method based on Bayesian optimization algorithm for small modular reactor	4
Preliminary study on TRU transmutation in VVER-1000 fuel assembly using MCNP6	4
Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage	3
Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method	3
A review on optimal UPFC device placement in electric power systems	3
Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)	3
Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research	3
Application research on neutron-gamma discrimination based on BC501A liquid scintillator	3
Drones application scenarios in a nuclear or radiological emergency	3
Automatic sentiment analysis of public opinion on nuclear energy	2
Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning	2

Finite element solution of the time-dependent SP3 equations using an implicit integration scheme	2
Determination of limiter design and material composition of MT-II spherical tokamak	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
A segmented γ scanning device and experimental research	2
Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers	2
The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface	2
Pool boiling performance of oxide nanofluid on a downward-facing heating surface	2
Simulations for L-STAR experimental gas-cooled system / CFD-Nachrechnung von L-STAR-Versuchen zur Wärmeübertragung von turbulenten Gasströmungen	2
FMEA for maintenance criterion at RSG-GAS reactor implemented on JE01-AP01 primary pump	2
Numerical simulation of the effect of rod bowing on critical heat flux	2
Editorial	2
Review and outlook of the integral test facility PKL III corresponding studies	2
"Full-Core" VVER-1000 calculation benchmark	2
Evaluation of human factor engineering influence in nuclear safety using probabilistic safety assessment techniques	2
SEDS benchmark for fuel rod behaviour during dry storage – preliminary results	2
Fuel integrity evaluation method for BWR-6 plant Kuosheng during ATWS events	1
Design and optimization of molten salt reactor monitoring system based on digital twin technology	1
Computational analysis of nuclear desalination system under various configurations	1
Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO2, MOX and (Th/U)O2 using OpenMC	1
Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation	1
Neutronics and both analytical and numerical solutions for the rod centered subchannel thermal-hydraulic model	1
Results of the ATHLET/BIPR-VVER software system (version 1.0) certification / Ergebnisse der Zertifizierung des Softwaresystems ATHLET/ BIPR-VVER (Version 1.0)	1
Experimental investigation on buffer/backfill materials for radioactive waste repository downward facing sorption additivity of cesium, strontium and cobalt with different concentrations	1
Analysis of the startup physics tests of a VVER-1200 reactor with the KARATE- 1200 code system	1
Fuel cycle of light water reactor with full consumption of recycled uranium	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
Research on the application of 22Na radiolocation detection technology in advanced manufacturing process control	1
Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology	1
A sustainable solution to ensure the dependently and safety of electrical grid relying on optimal allocation of UPFC for research reactor	1
Unfiltered air inleakage analysis of the control room envelope of Kuosheng nuclear power plant	1
Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code	1
Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer	1
Heat transfer enhancement of heat exchanger using rectangular channel with cavities	1
Lithium–lithium fusion evaporation research	1
Appraisal of new density coefficient on integrated-nanoparticles concrete in nuclear protection	1
Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia	1
CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle	1
GRS contributions to flow-induced vibrations related activities in Europe	1
The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition	1
Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA	1
CONTENTS	1
Criticality analysis for safety-critical software in nuclear power plant distributed control system	1
Solution of the VVER-1000 full core calculation benchmark by the KARATE code system	1
Summary of 3rd Sino-German symposium on fundamentals of advanced nuclear safety technology	1
Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor	1
Dynamic fault tree analysis of auxiliary feedwater system in a pressurized water reactor	1
Optimal operation strategy of LWR based on the PCI online prognosis model	1
New flow boiling frictional pressure drop multipliers for smooth and microfin tubes	1
Validation of new CMS5-VVER nuclear data library using critical experiments and X2 full-core benchmarkjh	1

Experimental and theoretical investigation of forced convection heat transfer with CNTs and CuO water based nano-fluids	1
CFD simulation on flow boiling in full scale 5 × 5 rod bundle	1
Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network	1
244Cm contributions to the alpha source term of CANDU reactors	1
Higher order TN approximation for the neutron diffusion problem in a slab reactor	1
Effect of gap design pressure on the LWR fuel rods lifetime	1
Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor	1
Effectiveness assessment of improvement measures in physical protection system monitoring center	1
Severe accident simulation for VVER-1000 reactor using ASTEC-V2.1.1.3	1
Heat transfer characterization under radial jet and falling film induced rewetting	1
Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor	1
Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code	1
Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor	1
Study of PWR hot leg creep rupture and RCS depressurization strategy during an SBO accident	1
The CANDLE burnup strategy applied to small modular pressurized water reactor loading with fully ceramic microencapsulated fuel	1
Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications	1
Photon dosimetry using selective data sampling with Particle Swarm optimization algorithm based on NaI(Tl) scintillation detector	1
Coupling MCNP6/ANSYS codes to calculate axial temperature and power distribution in a VVER-1000 fuel assembly	1
Research reactor model for isotope production based on the design of VVER-440 reactors	1
Investigation of the temporal rearrangement of zirconium hydride precipitates in cladding material for the interim and final storage period	1
New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV	1
Calendar of events	0
Optimization of power microfield distribution in JA profiles RK3+ fuel assemblies with 4.68% average enrichment for VVER-440 prospective fuel cycles	0
Calendar of events	0
Evaluation of the optimum safety performance of the nuclear reactor compact grounding system under lightning strikes and ground fault	0
Radiation heating of VVER-4440 thermocouple	0
ANSYS-CFX simulation of the SRBTL test loop core with nanofluid coolant	0
Impact of control rod insertion during burnup on PWR fuel assembly isotopic composition	0
Optimization strategy for SAM in nuclear power plants based on NSGA-II	0
Validation results of the BIPR-8A code, the new module of the software package KASKAD	0
Calendar of events	0
Implementation of the preCICE coupling interface for AC2/ATHLET	0
Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase	0
Probing 6He induced reactions with nuclear level density	0
Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system	0
Experimental study on boiling heat transfer of γ-Fe2O3 nanofluids on a downward heated surface	0
Positron annihilation lifetime spectroscopy of annealed tungsten	0
Calendar of events	0
Methodology for integral analysis of ATWS for Kuosheng nuclear power station	0
Frontmatter	0
Safety analysis for integrity enhancement in nuclear power plants (NPPs) in case of seashore region site	0
Pressurizer system dynamic model for transient control in PWR	0
Transient analysis of MTR research reactor during fast and slow loss of flow accident	0
Investigating the in-core 60Co production assembly for open pool type reactor	0
Analysis of the anticipated transient without scram (ATWS) initiated by emergency power mode through the full scope simulator	0
Frontmatter	0
Study of a perforated hollow cylinder and twisted tape inserts as a compound device in a circular tube for heat transfer enhancement	0
Frontmatter	0
Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage	0
Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water	0
Methodology for analyzing accidents with radioactive material release with code EPZDose	0
Characterization of polystyrene and polyacrylic based polymeric materials exposed to oxidative degradation	0
Calendar of events	0
Developing a futuristic multi-objective optimization of the fuel management problems for the nuclear research reactors	0
Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach	0
Calendar of events	0
Sensitivity of the neutron multiplication factor to water ingress into a spent fuel cask	0
Thermal hydraulic analysis of VVER spent fuels stored in vault dry system under different operating and design conditions	0
CFD modeling of natural convection in pebble bed geometry with finite volume method	0
Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)	0
An application research for near-surface repository of strontium-90 sorption kinetic model on mudrocks	0
Improvement of the passive efficiency calibration of the segmented gamma scanner	0
Extension to quadratic anisotropic scattering in one-speed neutron transport equation for critical thickness calculations / Berücksichtigung der quadratischen anisotropen Streuung bei der Lösung der 1	0
Monte Carlo calculations of different types of burnable poison rods used in PWR	0
Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor	0
Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition	0
Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology	0
The evaluation of TRACE/PARCS model for BWR-4 nuclear power plant by startup test transient analyses	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
Frontmatter	0
Neutronic analysis of the European sodium cooled fast reactor with Monte Carlo code OpenMC	0
Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration	0
Contents	0
Contents	0
Simulation of subcooled boiling in multiphase CFD code CFX / Simulation des unterkühlten Siedens im Mehrphasen-CFDCode CFX	0
Frontmatter	0
Scaling factors for CANDU reactor waste: how reliable are they?	0
Cycle extension in Slovak VVER-440 reactors to 14 months	0
CFD and machine learning based hybrid model for passive dilution of helium in a top ventilated compartment	0
Calendar of events	0

A non-dominated discrete differential evolution for fuel loading pattern optimization of a nuclear research reactor	0
Calendar of events	0
Application of internal fire probabilistic risk assessment in design optimization for marine SMR	0
Neutronic analysis of gadolinia bearing fuel assemblies	0
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	0
Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors	0
The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows	0
Note · Imprint	0
Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions	0
Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis	0
Frontmatter	0
The analysis of fire ignition frequency calculation for small modular light water reactors	0
Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR	0
Updating risk model for SGTR accident based on success criteria analysis	0
Calendar of events	0
Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor	0
Frontmatter	0
Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2019	0
Application of radio analytical tracer technique to study the performance of industrial grade ion exchange resin exposed to UV radiations	0
Effect of engraved concentric circles on pool boiling of water	0
Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core	0
Design of an unattended ore grading measurement system in a uranium mine	0
Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition	0
Study on specific heat capacity and thermal conductivity of uranium nitride	0
A Monte Carlo study on burnup treatment in sodium-cooled reactor with Th fuel	0
Assessment of the VVER-1200 reactivity coefficients on the basis of the data measured at the energy power levels	0
Development and usage of the digital SAMG system	0
Calendar of events	0
Contents	0
Analysis of 4-inch cold leg top-slot break LOCA in ATLAS experimental facility using MARS-KS	0
Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code	0
Large eddy fire simulation applications from nuclear industry	0
Contents	0
Safety assessment calculation procedure for operating VVER unit in maneuvering regimes	0
Validation of a new neutronics/thermal hydraulics coupling code for steady state analysis of light water reactors / Analyse stationärer Betriebsbedingungen in LWR durch gekoppelte Rechnungen	0
INHALT	0
Comparison of numerical and semi-analytical analyses of temperature fields of loaded dry casks	0
An investigation of multistream plate-fin heat exchanger modelling and design: a review	0
Study on the accidents analyses of a single channel for XADS by using MPC-LBE code	0
LOCA analysis of BWR-4/Mark-I nuclear power plant with TRACE	0
Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository	0
Temperature adjusted cross section libraries used for criticality calculations	0
Solution of Full-Core VVER-440 PK-3+ calculation benchmark by Serpent / Aktualisierte Referenzlösung des Berechnungsbenchmarks ,,PK-3+ Vollkern eines WWER-440" mit dem Programm Serpent	0
Role of impurity and thermal noise on the radiation sources in ITER using DT fuel	0
Coupled AC2-CFD simulations for a high-pressure core melt accident scenario	0
Development of a radioecological model for accidental release of radionuclides / Entwicklung eines radioökologischen Modells für die unfallbedingte Freisetzung von Radionukliden.	0
An artificial neural network-based numerical estimation of the boiling pressure drop of different refrigerants flowing in smooth and micro-fin tubes	0
Scientific inheritance of Eugenijus Ušpuras	0
Calendar of events	0
Numerical and experimental studies of the natural circulation mode during commissioning of Unit-1 Novovoronezh NPP-2	0
Frontmatter	0
A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis	0
Model of terminal debris bed formation after a CANDU core collapse	0
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	0
Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches	0
Comparison of back propagation network and radial basis function network in Departure from Nucleate Boiling Ratio (DNBR) calculation	0
Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor	0
INHALT	0
Frontmatter	0
Safety of Extended Dry Storage of Spent Nuclear Fuel SEDS2020: International online-workshop	0
The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning	0
Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC	0
Effect of metal layer height on heat transfer inside molten pool	0
Frontmatter	0
Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu an	0
An enhanced formalism for the inverse reactor kinetics problem	0
Calendar of events	0
A study of RCS depressurization strategy of CPR1000 SAMG	0
Calendar of events	0
Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor	0
Simulation of turbulent mixing rate in simulated subchannels of a reactor rod bundle	0
Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading	0
The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses	0
CONTENTS	0
Frontmatter	0
Improving of electric network feeding nuclear facility based on multiple types DGs placement	0
Study of cooling strategy for pressure vessel in pool research reactor at accident situation	0
Comparison of heat transfer in natural and forced circulation under rolling motion	0
Overview of metal seal tests performed at BAM and implications for extended interim storage	0
One-dimensional and three-dimensional coupling simulation research of centrifugal cascade hydraulics	0
Heat transfer and pressure drop analysis of a microchannel heat sink using nanofluids for energy applications	0
Design of Geiger Muller detector system for searching lost γ-ray source	0
Calculation studies of coated particles performance in sodium-cooled fast reactor	0
Maintaining safe continued operation of nuclear installations during pandemics / Aufrechterhaltung des sicheren Weiterbetriebs von Nuklearanlagen während Pandemien	0
Frontmatter	0
Establishment of analysis methodology for ionizing mattresses using RESRAD-BUILD code	0
Contents	0
INHALT	0
Sensitivity and uncertainty analysis for a radioecological model / Sensitivitäts- und Unsicherheitsanalyse eines radioökologischen Modells	0
Frontmatter	0
Effect of using graphene/water based nanofluid on heat transfer in heat exchangers with rotating straight inner tube	0
Study on calculation model and risk area of radionuclide diffusion in coastal waters under nuclear leakage accidents with different levels	0
Radiation shielding properties of mortars containing heavyweight particles	0
Establishment of analysis methodology of RADTRAD for Maanshan PWR ATWS	0
Enhanced heat transfer in corrugated plate fin heat sink	0