Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
《核工程与技术》（NET）是韩国核学会（KNS）的一份国际期刊，发表关于核科学与技术领域所有领域的原创研究、想法和发展的同行评审论文。NET双月刊发布原创文章、评论和技术说明。该杂志被列入汤森路透社的科学引文索引扩展版（SCIE）。NET涵盖了核能与辐射和平利用的所有领域，如下所示：1）反应堆物理2）热工水力学3）核安全4）核I&C 5）核物理、聚变和激光技术6）核燃料循环和放射性废物管理7）核燃料和反应堆材料8）辐射应用9）辐射防护10）核结构分析和电厂管理与维护11）核政策、经济学和人力资源开发
Gamma ray shielding characteristics and exposure buildup factor for some natural rocks using MCNP-5 code
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.05.013
Verification and validation of STREAM/RAST-K for PWR analysis
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.10.004
Research on the structure design of the LBE reactor coolant pump in the lead base heap
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.09.023
Improved PCA method for sensor fault detection and isolation in a nuclear power plant
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.08.020
Evaluation of dynamic behavior of coagulation-flocculation using hydrous ferric oxide for removal of radioactive nuclides in wastewater
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.11.016
Elasticity of substitution of renewable energy for nuclear power: Evidence from the Korean electricity industry
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.04.005
Comprehensive evaluation method for user interface design in nuclear power plant based on mental workload
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.10.010
Numerical investigation on vortex behavior in wire-wrapped fuel assembly for a sodium fast reactor
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.12.012
Numerical analysis on the rapid fire suppression using a water mist nozzle in a fire compartment with a door opening
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.10.026
Thermal transport study in actinide oxides with point defects
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.03.011
Synthesis of thorium tetrafluoride (ThF4) by ammonium hydrogen difluoride (NH4HF2)
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.12.023
Gamma radiation attenuation properties of tellurite glasses: A comparative study
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.06.014
Experimental validation of a nuclear forensics methodology for source reactor-type discrimination of chemically separated plutonium
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.11.003
Development of a drift-flux model based core thermal-hydraulics code for efficient high-fidelity multiphysics calculation
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.04.002
Room-temperature tensile strength and thermal shock behavior of spark plasma sintered W-K-TiC alloys
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.09.015
Proposal of residual stress mitigation in nuclear safety-related austenitic stainless steel TP304 pipe bended by local induction heating process via elastic-plastic finite element analysis
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.03.007
Evaluation of nuclear material accountability by the probability of detection for loss of Pu (LOPu) scenarios in pyroprocessing
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.08.015
Uranium thermochemical cycle used for hydrogen production
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.08.018
Stratified steam explosion energetics
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.08.019
Ambient dose equivalent measurement with a CsI(Tl) based electronic personal dosimeter
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.06.017
A classification of electrical component failures and their human error types in South Korean NPPs during last 10 years
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.12.011
Fluid effect on the modal characteristics of a square tank
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.01.012
PWSCC growth rate model of alloy 690 for head penetration nozzles of Korean PWRs
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.01.010
Studies on decomposition behavior of oxalic acid waste by UVC photo-Fenton advanced oxidation process
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.06.011
The corrosion of aluminium alloy and release of intermetallic particles in nuclear reactor emergency core coolant: Implications for clogging of sump strainers
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.02.012
Solving point burnup equations by Magnus method
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.01.006
Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.03.005
A novel approach in voltage transient technique for the measurement of electron mobility and mobility-lifetime product in CdZnTe detectors
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.12.024
Mathematical approach for optimization of magnetohydrodynamic circulation system
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.12.008
A study on the mechanically equivalent surrogate plate of UMo dispersion fuel using tungsten
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.10.015
A study on DCGL determination and the classification of contaminated areas for preliminary decommission planning of KEPCO-NF nuclear fuel fabrication facility
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.06.012
Development of a reference framework to assess stylized human intrusion scenarios using GENII Version 2 considering design features of planned near-surface disposal facility in Korea
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.04.019
Monte Carlo shielding evaluation of a CSNS Multi-Physics instrument
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.06.006
200 MeV Ag15+ ion beam irradiation induced modifications in spray deposited MoO3 thin films by fluence variation
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.06.004
Reprocessing of simulated voloxidized uranium–oxide SNF in the CARBEX process
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.05.020
Human resource planning for authorized inspection activity
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.10.017
Minimum detectable activity of plastic scintillator for in-situ beta measurement system in ground water
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.02.001
Study of n/γ discrimination using 3He proportional chamber in high gamma-ray fields
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.08.013
Logic tree approach for probabilistic typhoon wind hazard assessment
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.11.006
Simulation and design of individual neutron dosimeter and optimization of energy response using an array of semiconductor sensors
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.09.008
The investigation of a new fast timing system based on DRS4 waveform sampling system
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.10.001
Validation of the fuel rod performance analysis code FRIPAC
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.05.003
High heat flux limits of the fusion reactor water-cooled first wall
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.03.013
Effect of PT/CT contact on the circumferential temperature distribution over a fully voided nuclear channel of IPHWR
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.03.017
Prediction of flow boiling heat transfer coefficient in horizontal channels varying from conventional to small-diameter scales by genetic neural network
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.06.009
Employing high-temperature gas flux in a residual salt separation technique for pyroprocessing
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.05.023
A leak detection and 3D source localization method on a plant piping system by using multiple cameras
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.09.012
Improved nodal equivalence with leakage-corrected cross sections and discontinuity factors for PWR depletion analysis
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.02.013
Behavior characteristics of hydrogen and its isotope in molten salt of LiF-NaF-KF (FLiNaK)
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2018.10.008
Sorption characteristics of iodide on chalcocite and mackinawite under pH variations in alkaline conditions
来源期刊：Nuclear Engineering and TechnologyDOI：10.1016/J.NET.2019.01.014
