聚变工程资源库
检索带来源、版本、许可和访问条件的技术文档、科学软件与工程资源。
D–T聚变燃料循环技术报告
International Atomic Energy AgencyIAEA发布的D–T燃料循环等离子体物理与技术环节综述。
ITER工程基础手册
ITER Organization / EUROfusion系统整理ITER设计原则、技术设计基础、设计演进以及关键工程决策依据；当前已发布章节可逐项访问。
美国聚变科学与技术路线图
U.S. Department of Energy, Office of Science美国能源部发布的聚变科学与技术路线图，组织燃烧等离子体、极端环境工程和聚变能源利用等关键方向。
STEP原型电站概念设计工作流
UK Atomic Energy AuthorityUKAEA公开的STEP概念设计工作流，说明系统代码、等离子体模型与工程约束如何参与聚变电站设计迭代。
ITER装置控制设计手册
ITER Organization定义ITER装置仪控系统的标准、接口与集成要求，是理解CODAC及各装置系统控制协同的重要工程资料。
ITER真空手册
ITER Organization面向聚变装置真空系统设计、制造、装配、处理与安全要求的官方工程指南及附录入口。
聚变机器学习研究需求报告
U.S. Department of EnergyDOE聚变能源科学与先进科学计算研究联合发布的报告，系统梳理AI加速科学发现、聚变运行与数据基础的优先方向。
DOE聚变科学机器学习项目清单
U.S. Department of Energy涵盖EFIT-AI平衡重建、聚变材料机器学习、射频建模加速和实时等离子体预测等研究项目。
GS2科学软件单元测试方法
York Plasma Institute, University of York介绍如何使用pFUnit为GS2等离子体模拟软件建立快速、可重复的单元测试，为科学软件验证、持续集成与结果可信度提供工程方法。
OpenMC软件论文
Annals of Nuclear Energy记录OpenMC蒙特卡罗粒子输运能力、软件架构和研究用途的同行评议论文。
MOOSE框架论文
Nuclear Engineering and Design介绍MOOSE多物理框架架构与耦合求解基础的同行评议论文。
ITER建造与制造进展图集
ITER Organization覆盖ITER建造、制造与装配过程的官方图集，适合核对部件形态、制造环节和工程实施进展。
EUROfusion研究报告库
EUROfusionEUROfusion发布的项目报告与计划资料入口，覆盖欧洲聚变研究路线、装置计划和工程研发进展。
FAIR-MAST聚变实验数据管理系统
UK Atomic Energy AuthorityUKAEA公开的聚变实验数据管理研究，面向可发现、可访问、可互操作、可复用的数据及AI/ML应用基础。
IAEA AI for Fusion研究协作资料
International Atomic Energy AgencyIAEA AI for Fusion协作研究项目会议与公开资料入口，汇集机器学习、聚变数据和跨机构研究议题。
聚变等离子体破裂深度学习预测
U.S. Department of EnergyDOE公开研究说明，介绍利用DIII-D与JET数据开展跨装置托卡马克破裂预测的方法与应用背景。
Beam transmission design for a 120 keV and 15 MW neutral beam injection system for burning plasma tokamak
Plasma Physics and Controlled FusionAbstract For tokamak devices, neutral beam injection (NBI) remains an important method for heating and current drive. In this paper, the beam transmission model based on positive ion source neutral beam injector (P-NBI) is constructed using the Monte Carlo…
The Roadmap for runaway electron-induced plasma facing component damage in tokamaks
Plasma Physics and Controlled FusionAbstract This Roadmap article addresses the critical and multifaceted challenge of plasma-facing component (PFC) damage caused by runaway electrons (REs) in tokamaks, a phenomenon that poses a significant threat to the viability and longevity of future fusi…
Energetic particle driven Alfvén eigenmodes and associated energetic particle redistribution in a tokamak burning plasma
Nuclear FusionAbstract Energetic-particle driven Alfvén eigenmodes (AEs) and associated redistribution of energetic particles in phase space are investigated using kinetic-magnetohydrodynamic (MHD) hybrid simulations for a tokamak burning plasma with weakly reversed magn…
An Overview of Magnetic Confinement Fusion:Tokamak, Stellarator, Reversed-Field Pinch, Field-Reversed Configuration, Magnetic Mirror
SuperconductivityMagnetic confinement fusion (MCF) is widely regarded as a promising pathway toward achieving sustainable and large-scale clean energy production. This paper presents a comprehensive review of the fundamental principles, major configurations, historical evol…
Readiness of Tritium Handling Technology for Fusion Energy Systems
Fusion Science & TechnologyAt the present time more than 50 companies have undertaken the quest to develop fusion energy systems using a variety of approaches including magnetic confinement schemes such as tokamaks, stellarators, reverse field configurations, mirrors, and inertial co…
MHD, disruptions and control physics: Chapter 4 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract In this chapter, we review the progress in MHD stability, disruptions and control in magnetic fusion research that has occurred over the past (more than) one and a half decades since the publication by Hender et al in 2007 on the same topic as part…
Upgrades and characteristics of the compact torus injector for central fueling of the EAST tokamak
Plasma Science and TechnologyAbstract The compact torus injector (CTI) for the central fueling of the EAST tokamak has undergone significant upgrades to enhance its injection capability. During the initial phase of the platform testing phase, EAST-CTI demonstrated relatively low perfor…
Runaway electron-induced plasma facing component damage in tokamaks
arXivThis Roadmap article addresses the critical and multifaceted challenge of plasma-facing component (PFC) damage caused by runaway electrons (REs) in tokamaks, a phenomenon that poses a significant threat to the viability and longevity of future fusion reacto…