Fusion Science and Technology, a research journal of the American Nuclear Society, publishes original research and review papers on fusion plasma physics and plasma engineering, fusion nuclear technology and materials science, fusion plasma enabling science technology, fusion applications, and fusion design and systems studies.
《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。
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
