Nuclear Engineering and Technology
ISSN:1738-5733

Nuclear Engineering and Technology

NUCL ENG TECHNOL
学科领域:工程技术
是否预警:不在预警名单内
是否OA:
录用周期:较慢,6-12周
新锐分区:工程技术3区
年发文量:547
影响因子:2.6
JCR分区:Q1

基本信息

《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
1738-5733SCIE/Scopus收录/DOAJ开放期刊
2.6
2.7
2026年3月发布
点击查看历史分区趋势    >
大类学科小类学科Top期刊综述期刊
工程技术3区
NUCLEAR SCIENCE & TECHNOLOGY 核科学技术
2区
N/A
WOS期刊SCI分区  2024-2025最新升级版
按JIF指标学科分区收集子录JIF分区JIF排名百分位
学科:NUCLEAR SCIENCE & TECHNOLOGY
SCIE
Q1
7/41
按JCR指标学科分区收集子录JCR分区JCR排名百分位
学科:NUCLEAR SCIENCE & TECHNOLOGY
SCIE
Q1
3/41
29
547
18%容易较慢,6-12周-工程技术-核科学技术
11.5%
时间预警情况
2026年03月发布的新锐学术版不在预警名单中
2025年03月发布的2025版不在预警名单中
2024年02月发布的2024版不在预警名单中
2023年01月发布的2023版不在预警名单中
2021年12月发布的2021版不在预警名单中
2020年12月发布的2020版不在预警名单中
98.17%98.4%0.3%
CiteScore:4.90
SJR:0.692
SNIP:1.383
学科类别分区排名百分位
大类:Energy
小类:Nuclear Energy and Engineering
Q1
16 / 80

期刊高被引文献

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

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