FUSION SCIENCE AND TECHNOLOGY
ISSN:1536-1055

FUSION SCIENCE AND TECHNOLOGY

FUSION SCI 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:一般,3-6周
新锐分区:工程技术4区
年发文量:61
影响因子:1.2
JCR分区:Q3

基本信息

《聚变科学与技术》(Fusion Science and Technology)是美国核学会的研究期刊,发表有关聚变等离子体物理和等离子体工程、聚变核技术和材料科学、聚变等离子体使能科学技术、聚变应用、聚变设计和系统研究的原创研究和评论论文。
1536-1055SCIE/Scopus收录
1.2
1.1
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4区
NUCLEAR SCIENCE & TECHNOLOGY 核科学技术
3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
Q3
28/41
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
Q3
24/41
44
61
-容易一般,3-6周-工程技术-核科学技术
8.3%
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
93.44%12.16%0.85%
CiteScore:2.10
SJR:0.453
SNIP:0.947
学科类别分区排名百分位
大类:Energy
小类:Nuclear Energy and Engineering
Q3
41 / 80
大类:Energy
小类:Nuclear and High Energy Physics
Q3
49 / 91
大类:Energy
小类:Mechanical Engineering
Q3
416 / 720
大类:Energy
小类:Civil and Structural Engineering
Q3
241 / 407
大类:Energy
小类:General Materials Science
Q3
312 / 460

期刊高被引文献

PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1602390
Existing Source for Muon-Catalyzed Nuclear Fusion Can Give Megawatt Thermal Fusion Generator
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1546090
Integrated Liquid Metal Flowing First Wall and Open-Surface Divertor for Fusion Nuclear Science Facility: Concept, Design, and Analysis
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1610649
The ITER Tokamak Exhaust Processing System Design and Substantiation
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1642089
Tritium Supply and Processing for the First KATRIN Tritium Operation
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1705681
Summary of the FESAC Transformative Enabling Capabilities Panel Report
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1565912
Design and Analysis of the Liquid Metal Free-Surface Divertor Cooling System
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1643689
Initial Neutronics Investigation of a Liquid-Metal Plasma-Facing Fusion Nuclear Science Facility
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1600930
Design of Two Experimental Mock-Ups as Proof-of-Concept and Validation Test Rigs for the Enhanced EU DEMO HCPB Blanket
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1629247
Design and Analysis of a Divertor Langmuir Probe for ITER
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1520577
Engineering Challenges of Wendelstein 7-X Mechanical Monitoring During Second Phase of Operation
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1623568
Discrete Element Analysis of Heat Transfer in the Breeder Beds of the European Solid Breeder Blanket Concept
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1565481
Simulation Study on the Wide-Range Measuring Algorithm in ITER Neutron Flux Monitor
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1526026
Improvement of the Neutron Production Rate of IEC Fusion Device by the Fusion Reaction on the Inner Surface of the IEC Chamber
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1609821
Impact of Outer Fuel Cycle Tritium Transport on Initial Start-Up Inventory for Next Fusion Devices
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1643691
Modeling the Edge-Plasma Interface for Liquid-Lithium Walls in FNSF
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1643686
Mechanical Design Concept of Superconducting Magnet System for Helical Fusion Reactor
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1603041
High-Heat-Flux Target Design for the Material Plasma Exposure eXperiment
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1637239
Periodic Surface Morphology Characteristics of Tungsten Under Simultaneous Helium and Deuterium Bombardment at 30 keV
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1602397
Surface Erosion of Plasma-Facing Materials Using an Electrothermal Plasma Source and Ion Beam Micro-Trenches
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1623570
Characterization of Arc Plasma by Movable Single and Double Langmuir Probes
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1579623
The ITER Tokamak Exhaust Processing System Permeator and Palladium Membrane Reactor Design
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1629249
Status of ITER Safety Issues
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1594538
Neutronics Scoping Studies for Experimental Fusion Devices
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1613141
A 6 MW/m2 High Heat Flux Testing Facility of Irradiated Materials Using Infrared Plasma-Arc Lamps
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1623571
A Particle-, Momentum-, and Energy-Conserving Fluid Transport Theory for the Tokamak Plasma Edge
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1574529
High-Temperature Creep Properties of SiC Fibers with Different Compositions
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1647029
Simulation of the Divertor Target Shielding During Major Disruption in DEMO
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1643684
Neutronics Calculations for a Hypothetical Plasma-Jet-Driven Magneto-Inertial-Fusion Reactor
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1613140
Distribution of Tritium in the Near Surface of Type 316 Stainless Steel
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1644136
Radiation Protection Design and Licensing for an Experimental Fusion Facility: The Italian and European Approaches
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1608097
Overview of the Systems Engineering Process as it Applies to NSTX-U
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1643685
Neutronic Analysis for Feasibility of Fusion-Driven Subcritical System with Constant Fusion Power by Online Feeding of Molten Salt Fuel
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1609820
Electrical Insulation Tape Winding and Inspection System
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1622989
Assessment of Activation on Level L3 of the Tokamak Building due to the ITER Tokamak Cooling Water System
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1606519
Design and Analysis of the US ITER Central Solenoid Module Lifting Fixture
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1629250
The Effect of Heat Treatment on the Properties of SiCf/SiC Composites Prepared with Different SiC Fibers
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1533620
ADDENDUM: About a New Fusion Reactor Scheme
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1622973
Different Methods for Assessing System Failure Criticality in the RAMI Approach
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1603534
Safety of Air Detritiation System Operation
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1499396
Development of Real-Time Software for Thomson Scattering Analysis at NSTX-U
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1658037
Tritium Extraction from Water
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1658482
The DTEQ Code for Toroidal MHD Equilibria with Diamagnetic Current Modeling Using the deal.II Finite Element Library
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1554391
Alarm System for EAST Poloidal Field Power Supply
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1506625
Takagi Sugeno Fuzzy Controller for ITER Poloidal Field ac/dc Converter Using Active Power Filter
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1565732
Beam Ion–Driven Alfvén Instabilities in T-15 Baseline Scenario
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1562315
Preliminary Reliability Allocation Method for Fusion Facility Based on Probabilistic Safety Assessment
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1647082
An Experimental Reversed Heat Flux Investigation of the Helium-Cooled Modular Divertor with Multiple Jets
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1643683
Study of Corrosion Behaviors of 316L Stainless Steel Welds in Liquid Lithium with Hydrogen Impurity
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2018.1533618
Vapor Shielding Effect on DEMO Divertor
来源期刊:Fusion Science and TechnologyDOI:10.1080/15361055.2019.1610291

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