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NUCLEAR ENGINEERING AND DESIGN
ISSN：0029-5493

NUCLEAR ENGINEERING AND DESIGN

NUCL ENG DES
学科领域：工程技术
是否预警：不在预警名单内
是否OA：否
录用周期：约5.4个月
新锐分区：工程技术3区
年发文量：779
影响因子：2.1
JCR分区：Q2

基本信息

核工程和设计涵盖了核裂变反应堆工程、设计、安全和建造方面的广泛学科。反应堆设计基础包括：·热工水力学和堆芯物理学·安全分析、风险评估（PSA）·结构和机械工程·材料科学·燃料行为和设计·结构工厂设计·反应堆部件工程·实验反应堆设计基础以外的方面包括：·事故缓解措施·反应堆控制系统·许可证发放问题·安全防护工程·工厂经济性·后处理/废物处理·核能应用·维护·退役关于新反应堆想法和发展（第四代反应堆）的论文将被考虑，如本质安全模块化HTR、高性能LWR/HWR和LMFB/GFR;锕系元素燃烧器、加速器驱动系统、能量放大器和其他特殊设计的动力和研究反应堆及其应用也受到鼓励。
0029-5493SCIE/Scopus收录
2.1
点击查看最新影响趋势>
2.2
新
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
3区
否
N/A
新
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
Q2
11/41
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
9/41
87
779
点击查看年发文量趋势图>
18%容易约5.4个月-工程技术-核科学技术
23.8%
点击查看自引率趋势图>
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
97.69%14.31%0.67%
CiteScore：3.40
SJR：0.772
SNIP：1.417
学科类别分区排名百分位
大类：Energy
小类：Nuclear Energy and Engineering
Q2
28 / 80
大类：Energy
小类：Nuclear and High Energy Physics
Q2
33 / 91
大类：Energy
小类：Safety, Risk, Reliability and Quality
Q2
91 / 235
大类：Energy
小类：Mechanical Engineering
Q2
306 / 720
大类：Energy
小类：Waste Management and Disposal
Q2
75 / 150
大类：Energy
小类：General Materials Science
Q3
258 / 460

期刊高被引文献

High-fidelity PIV measurement of cross flow in 5 × 5 rod bundle with mixing vane grids
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.01.021
Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part II: whole-core analysis
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.03.004
Characterization of the gas-liquid interfacial waves in vertical upward co-current annular flows
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.03.008
Design directions of optimized reactivity control systems in sodium fast reactors
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2018.11.008
Current status of research on heat transfer in forced convection of fluids at supercritical pressures
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.110207
Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.03.022
Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.110237
Numerical study on the characteristics of single wetted flat wire with single droplet impact under the disturbance of airflow
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.01.029
Natural convection heat transfer from a vertical single cylinder with helical wire spacer in liquid sodium
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2018.10.019
A baseline closure concept for simulating bubbly flow with phase change: A mechanistic model for interphase heat transfer coefficient
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.04.007
Current state of in-cabinet response spectra for seismic qualification of equipment in nuclear power plants
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2018.12.017
Gap conductance modeling I: Theoretical considerations for single- and multi-component gases in curvilinear coordinates
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.110283
Numerical simulation of multicomponent flows with the presence of density gradients for the upgrading of advanced turbulence models
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.01.025
Numerical simulation study on the opening process of the atmospheric relief valve
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.05.034
Uncertainty Quantification method for CFD applied to the turbulent mixing of two water layers – II: Deterministic Sampling for input uncertainty
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.04.016
Evaluation of local damage to reinforced concrete panels subjected to oblique impact by soft missile
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.04.024
Helium leak detection method using ambient temperature of canister top
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.05.031
On the mechanism of final heat transfer restoration at the transition to gas-like fluid at supercritical pressure: A description by CFD analyses
来源期刊：Nuclear Engineering and DesignDOI：10.1016/j.nucengdes.2019.110345
Site evaluation for nuclear power plants – The practices
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.06.002
A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2018.12.011
Dryout prediction with CFD model of annular two-phase flow
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.04.020
Impact of uncertainties on the safety performances of the LBE-XADS concept nuclear reactor
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2018.10.016
Analysis of the Effect of MELCOR Modelling Parameters on In-Vessel Accident Progression in Nordic BWR
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.04.040
Numerical study on the shear failure behavior of RC beams subjected to drying
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.06.003
Core thermal hydraulic CFD support for liquid metal reactors
来源期刊：Nuclear Engineering and DesignDOI：10.1016/j.nucengdes.2019.110322
CFD simulation on the flow and heat transfer characteristics of mist flow in wire-wrapped rod bundle
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.02.003
Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR
来源期刊：Nuclear Engineering and DesignDOI：10.1016/j.nucengdes.2019.110317
Experimental study on natural convection heat transfer in a two-layer corium pool based on COPRA facility
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.04.031
System code analysis of accumulator nitrogen discharge during LOCA experiment at PWR PACTEL test facility
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.110288
A best-estimated correlation for prediction of nucleation radius in sodium boiling
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.02.009
Seismic performance of an idealized steel-plate composite (SC) modular structure subjected to accident thermal loading
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.05.029
Coaxial stacking disjoint model study of 10 MW high temperature gas-cooled reactor (HTR-10)
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.110193
Determination of pressure loss coefficient of the hot duct break of the CEA ALLEGRO 2009 concept using a CFD technique
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.05.016
Development and application of SANPR with coupling numerical methods for analysis of effect of moving condition on natural circulation of nuclear power system
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.04.030
Experimental and numerical study to optimize a design of passive moderator cooling system of an advanced nuclear reactor
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.05.023
Experimental investigation of accidental scenarios using a scale water model of a HLM reactor
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.02.016
High-fidelity experimental measurements for modeling and simulation of nuclear engineering applications
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.110181
Fragmentation characteristics of molten materials jet dropped into liquid sodium pool
来源期刊：Nuclear Engineering and DesignDOI：10.1016/j.nucengdes.2019.110348
An engineering model and its numerical validation for a malevolent aircraft impinging against a rigid target: Force and impulse estimations
来源期刊：Nuclear Engineering and DesignDOI：10.1016/j.nucengdes.2018.11.034
Oxidation during fuel-coolant interaction: Advances and modeling
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.02.008
Numerical investigation on the influence of the type of PI controller combined with MAAP code on the steady-state performance of a nuclear power plant
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.01.004
RISMC industry application #1 (ECCS/LOCA): Core characterization automation: Lattice codes interface for PHISICS/RELAP5-3D
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.02.005
Prediction of fundamental frequency of PWR fuel assembly in End-Of-Life condition using lateral bending test data
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.01.028
Stability performance of steel liner domes of nuclear reactor containment during construction
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.05.018
Scaling ability of the counter-current flow limitation (CCFL) correlations for application to reactor thermal hydraulics
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.110226
REMOVED: Automated global variance reduction method based on discrete ordinates: Functionality, validation, application
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.05.027
Reactivity analysis of a direct nuclear heated gas turbine with nitrogen coolants
来源期刊：Nuclear Engineering and DesignDOI：10.1016/j.nucengdes.2019.110355
Sensitivity analysis and application of advanced nuclear accounting methodologies on the high reliability safeguards model: Use of discrete event simulation for material throughput in fuel fabrication
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.01.016
Study on added mass model for fluid-structure interaction of spent fuel storage rack
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.110224
A multi-scale and multi-physics simulation methodology with the state-of-the-art tools for safety analysis in Light Water Reactors applied to a Turbine Trip scenario (Part II)
来源期刊：Nuclear Engineering and DesignDOI：10.1016/J.NUCENGDES.2019.05.008

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新
2026年3月发布（新锐分区）
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
3区
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2025年3月升级版
大类学科小类学科Top期刊综述期刊
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NUCLEAR SCIENCE & TECHNOLOGY 核科学技术
3区
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否
2023年12月旧的升级版
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工程技术3区
NUCLEAR SCIENCE & TECHNOLOGY 核科学技术
2区
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