Kerntechnik
Kerntechnik is a journal indexed in SJR in Materials Science (miscellaneous) and Nuclear Energy and Engineering with an H index of 21. It has an SJR impact factor of 0,26 and it has a best quartile of Q3. It is published in English. It has an SJR impact factor of 0,26.
Metrics
Scimago and CountryOfPapers database fields
SJR Impact
0,26
H-index
21
Docs (year)
70
Docs 3y
176
Total refs
1883
Cites 3y
179
Citable 3y
175
Cites/Doc 2y
1.22
Ref/Doc
26.9
Immediate OA
—
Embargoed OA
NPD
Non OA / Submission
—
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Researcher reviews
Best articles by citations
Analysis of the CSF model for simulated loss of coolant accident conditions
View moreValidation of radioactive isotope activity measurement in homogeneous waste drum using Monte Carlo codes
View moreCFD analysis on mixing effects of spacer grids with different dimples and sizes for advanced fuel assemblies
View moreCalculation of the fuel temperature coefficient of reactivity considering non-uniform radial temperature distribution in the fuel rod
View moreAxial enrichment profile in advance nuclear energy power plant at supercritical-pressures
View moreAtomistic nano-scale 3D simulations about effects of Cr percentage on the molecular dynamics parameters of Fe-9-12% Cr alloys at fusion reactor temperature conditions
View moreAssessment of the uncertainties of MULTICELL calculations by the OECD NEA UAM PWR pin cell burnup benchmark
View moreApplying full multigroup cell characteristics from MCU code to finite difference calculations of neutron field in VVER core
View moreApplication of the new IAPWS Guideline on the fast and accurate calculation of steam and water properties with the Spline-Based Table Look-Up Method (SBTL) in RELAP-7
View moreApplication of the method for uncertainty and sensitivity evaluation to results of PWR LBLOCA analysis calculated with the code ATHLET. Part 2: sensitivity analysis
View moreAnalytical investigation of lignite and its ash samples taken from the Afsin-Elbistan coal basin in Turkey
View moreAnalysis of the source term formation in a severe accident initiated by end fitting failure in CANDU type reactors
View moreAnalysis of the flow instability among channels of the OTSG in the naval craft NPP
View more3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions
View moreAnalysis of heterogeneous boron dilution transients during outages with APROS 3D nodal core model
View moreAnalysis of heat transfer under high heat flux nucleate boiling conditions
View moreAnalyses of Beyond Design Basis Accident Homogeneous Boron Dilution Scenarios
View moreAn investigation of the effect of the upper beryllium reflector on the moderator temperature coefficient of reactivity of miniature neutron source reactors
View moreAn experimental investigation on dynamics and heat transfer associated with a single droplet impacting on a hot surface above the Leidenfrost point temperature
View moreAn analytical approach for a nodal formulation of a two-dimensional fixed-source neutron transport problem in heterogeneous medium
View moreAn analysis of reactivity prediction during the reactor start-up process
View moreA model-based approach to operational event groups ranking
View moreA finite volume approach to the problem of heat transfer in axisymmetric annulus geometry with internal heating element using local analytical solution techniques
View moreA comparison study for mass attenuation coefficients of some amino acids using MCNP code
View more