Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).
Kerntechnik是一本独立的核工程杂志（包括核电站、研究反应堆和模拟器的设计、运行、安全和经济）、能源系统、辐射（工业、医学和研究中的电离辐射）和辐射防护（电离辐射的生物效应，职业、医疗和公众照射的防护制度，剂量评估，运行保护和安全计划、放射性废物管理、退役和监管要求）。
Development of AC2 for the simulation of advanced reactor design of Generation 3/3+ and light water cooled SMRs
来源期刊：KerntechnikDOI：10.3139/124.190068
Validation of the AC2 Codes ATHLET and ATHLET-CD
来源期刊：KerntechnikDOI：10.3139/124.190069
Natural radioactive risk assessment in top soil and possible health effect in Minim and Martap villages, Cameroon: using radioactive risk index and statistical analysis
来源期刊：KerntechnikDOI：10.3139/124.110927
New research reactor protection system
来源期刊：KerntechnikDOI：10.3139/124.110935
Core loading optimisation in Slovak VVER-440 reactors
来源期刊：KerntechnikDOI：10.3139/124.190024
Statistical evaluation of C-15 cycles in Paks NPP, based on measured in-core data
来源期刊：KerntechnikDOI：10.3139/124.190028
ATWS severe accident analysis in the loss of flow scenario using the MELCOR code in Bushehr nuclear Power Plant
来源期刊：KerntechnikDOI：10.3139/124.110914
Validation and Application of the AC2 Code COCOSYS
来源期刊：KerntechnikDOI：10.3139/124.190066
Effect of reactor operator intervention during unprotected LOFA in a typical MTR
来源期刊：KerntechnikDOI：10.3139/124.110874
Numerical study on cut-off diameter of aerosol particle for filtered containment venting system in nuclear power plant
来源期刊：KerntechnikDOI：10.3139/124.110971
Seasonally gross alpha and beta activity concentration in bottom and mid-depth water in Sır Dam Pond (Kahramanmaras, Turkey)
来源期刊：KerntechnikDOI：10.3139/124.110984
Numerical prediction of single-phase flow mixing characteristics in a 1/12th of the cross segment of a 54-rod bundle
来源期刊：KerntechnikDOI：10.3139/124.110977
Method based on directed graph and binary decision diagram to break logic loops
来源期刊：KerntechnikDOI：10.3139/124.110921
Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320
来源期刊：KerntechnikDOI：10.3139/124.190015
Experimental study on penetration characteristic of submerged steam jet in quiescent water
来源期刊：KerntechnikDOI：10.3139/124.190036
Validation of COCOSYS 2.4v4 AIM module on various single effect and integral experiments
来源期刊：KerntechnikDOI：10.3139/124.190045
Adaptation of the gas gap simplified model in DYN3D code to new types of fuel
来源期刊：KerntechnikDOI：10.3139/124.190029
CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications
来源期刊：KerntechnikDOI：10.3139/124.190060
Prospects for implementation of VVER nuclear fuel enriched above 5%
来源期刊：KerntechnikDOI：10.3139/124.190023
Reanalysis of environmental qualification radiation parameters for Kuosheng nuclear power plant
来源期刊：KerntechnikDOI：10.3139/124.110961
Ultimate response guideline strategy evaluation for Maanshan power plant
来源期刊：KerntechnikDOI：10.3139/124.110891
C-PORCA 7: a nodal diffusion reactor calculation code to support off-line and on-line core analysis at Paks nuclear power plant
来源期刊：KerntechnikDOI：10.3139/124.190021
Flow and heat transfer characteristics in rough micro-channels
来源期刊：KerntechnikDOI：10.3139/124.190001
VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6
来源期刊：KerntechnikDOI：10.3139/124.190041
Criticality safety analysis for GNS IQ® – The Integrated Quiver System for damaged fuel
来源期刊：KerntechnikDOI：10.3139/124.190032
Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2018
来源期刊：KerntechnikDOI：10.3139/124.019041
Analysis of the melt spreading and MCCI during the ex-vessel phase of a severe accident in WWER-1000
来源期刊：KerntechnikDOI：10.3139/124.190010
CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications
来源期刊：KerntechnikDOI：10.3139/kern-2019-840607
Flow and heat transfer characteristics in rough micro-channels
来源期刊：KerntechnikDOI：10.3139/kern-2019-840609
Control rod material effect on safety parameters of research reactors
来源期刊：KerntechnikDOI：10.3139/124.110989
Benchmark study of OPAL research reactor using MCNP codes
来源期刊：KerntechnikDOI：10.3139/124.190037
Comparative analysis of simulations of LIVE-L10 and -L11 experiments using different lower head modules of AC2
来源期刊：KerntechnikDOI：10.3139/124.190034
Benchmark study of OPAL research reactor using MCNP codes
来源期刊：KerntechnikDOI：10.3139/kern-2019-840605
Method based on directed graph and binary decision diagram to break logic loops
来源期刊：KerntechnikDOI：10.3139/kern-2019-840606
Operating experience feedback from incidental fluctuations of the power measurement channel at ETRR-2
来源期刊：KerntechnikDOI：10.3139/kern-2019-840604
Assessment of the fuel assembly pin-by-pin model in the KORSAR/GP code
来源期刊：KerntechnikDOI：10.3139/124.190027
TRACE simulations of IIST cooldown experiments
来源期刊：KerntechnikDOI：10.3139/kern-2019-840608
TRACE simulations of IIST cooldown experiments
来源期刊：KerntechnikDOI：10.3139/124.190090
Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system
来源期刊：KerntechnikDOI：10.3139/kern-2019-840610
Fuel cycles with PK-3+ FAs for VVER-440 reactors
来源期刊：KerntechnikDOI：10.3139/124.190022
Assessment of the health damage costs of radionuclides releases from Muğla provinces lignite-fired power plants
来源期刊：KerntechnikDOI：10.3139/124.110924
GRS Code System AC2
来源期刊：KerntechnikDOI：10.3139/124.019051
Operating experience feedback from incidental fluctuations of the power measurement channel at ETRR-2
来源期刊：KerntechnikDOI：10.3139/124.190053
Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system
来源期刊：KerntechnikDOI：10.3139/124.190062
The core shroud leakage analysis and study for Kuosheng nuclear power plant
来源期刊：KerntechnikDOI：10.3139/124.110986
Leningrad NPP-2 start-up loss of power test and its simulation with use of KORSAR/GP code
来源期刊：KerntechnikDOI：10.3139/124.190026
Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident
来源期刊：KerntechnikDOI：10.3139/124.110979
New developments in the thermal hydraulic module THY of the COCOSYS program, part of the AC2 software package: turbulence in gaseous countercurrent flows
来源期刊：KerntechnikDOI：10.3139/124.190078
Research on multi-scale simulation model for single-phase water pipe networks
来源期刊：KerntechnikDOI：10.3139/124.110997
Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies
来源期刊：KerntechnikDOI：10.3139/124.190019
