聚变科学与工程资源库
检索物理代码、实验数据、代理模型、工程几何、技术文档与验证资料，并核对来源、版本和使用条件。
快离子ITG湍流稳定化代理模型
Google DeepMind用于估计离子回旋共振加热产生的快离子对ITG湍流临界梯度影响，支持氢与氦-3快离子工况，并可与输运代理模型组合使用。
KARHU边界区MHD稳定性代理模型
DigiFusion面向理想剥离-气球模MHD稳定性分析的机器学习代理模型，用于近似MISHKA稳定性计算，并提供DIII-D、JET及跨装置模型权重。
TokaMark等离子体诊断鲁棒性模型集
TokaMark Robustness Research Project基于MAST托卡马克诊断数据训练的模型检查点集合，用于比较XGBoost、LSTM、Transformer和CNN在传感器缺失与信号异常条件下的预测表现。
OpenMC 官方文档
OpenMC Development TeamOpenMC蒙特卡罗粒子输运软件的安装、建模、运行和开发文档入口。
MOOSE 多物理框架
Idaho National Laboratory面向耦合非线性方程组的并行多物理有限元框架及官方文档。
GENE 回旋动理学代码
GENE Development Team用于等离子体微观湍流与输运研究的回旋动理学代码官方入口。
JOREK 非线性MHD代码
JOREK Team用于托卡马克非线性MHD现象研究的代码、出版物和项目资料入口。
SOLPS-ITER 文档
SOLPS-ITER Community面向托卡马克边缘等离子体与中性粒子建模的软件文档入口。
PROCESS 系统设计文档
UK Atomic Energy Authority聚变电站系统级设计点、功率流与工程权衡模型的官方文档入口。
FUSE聚变集成设计框架
FUSE Development Team用于聚变装置集成仿真、设计点研究、场景优化和模型验证的开源Julia框架。
Open FUSION Toolkit
Open FUSION Toolkit Team面向等离子体与聚变工程二维/三维问题的有限元工具集，包含平衡、薄壁电磁和扩展MHD等求解组件。
DESC仿星器平衡与优化套件
PlasmaControl面向三维磁流体平衡求解与仿星器优化的开源软件，采用伪谱方法和自动微分支持平衡计算、目标函数优化及设计研究。
FreeGSNKE托卡马克自由边界平衡模拟
Fusion Computing Lab用于托卡马克自由边界等离子体平衡计算的Python开源软件，支持静态正向与反向问题，以及随时间演化的正向平衡模拟。
BOUT++等离子体流体模拟框架
BOUT++ Development Team面向曲线坐标系中等离子体流体模拟的开源框架，通过模块化空间离散、时间积分和物理模型支持边缘等离子体与非线性流体研究。
Progress and innovations in the TCV tokamak research programme
DOE OSTI已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。
Integration of X-point radiator divertor operation with high beta hybrid core plasmas in DIII-D
DOE OSTI已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。
Development of mechanically jointed plasma facing component for divertor plates
Elsevier BV已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。
A snowflake divertor: a possible solution to the power exhaust problem for tokamaks
IOP Publishing已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。
Overview of the KSTAR experiments and future plan
DOE OSTI已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。
Investigation of Drift Effects in UEDGE Simulations of NSTX-U Edge Plasma With Lithium Divertors
WileyLithium is a low-Z material, and lithium-based plasma-facing components (PFCs) are planned for the National Spherical Torus Experiment Upgrade (NSTX-U) to explore potential benefits for divertor power exhaust and core plasma management. NSTX-U is a medium-sized spherical tokamak with up to 12 MW of auxiliary heating, capable of generating reactor-relevant plasma conditions. This work presents boundary plasma simulations for NSTX-U with lithium PFCs using the UEDGE code, incorporating full magnetic and E ×B drift physics. The simulations show that drifts strongly influence heat and particle transport: they enhance convective transport, broaden the scrape-off layer heat-flux width λ<sub>q</sub> , and reduce the anomalous heat diffusivity χ required to reproduce predicted SOL heat-flux width. E ×B drifts provide poloidal transport, while ∇B (which includes both gradB and curvature) drifts provide radial heat and particle transport. Lithium transport is also affected by drifts, with lithium ions migrating from the outer divertor to the inner divertor through the private flux region (PFR) following the E ×B drifts flow, lowering upstream impurity lithium densities. UEDGE is self-consistently coupled with the Wall-Li model to study plasma lithium PFC interactions depending on the local lithium sourcing based on local plasma conditions and lithium surface temperature. In these simulations, lithium evaporation shows a vapor-shielding effect that reduces divertor heat flux and increases radiative losses once surface temperatures exceed 450°C. This research work provides a first step toward self-consistent modeling of lithium PFCs in NSTX-U, demonstrating the impact of drift-driven plasma transport in SOL and divertor regions.
ANALYTIC EXPRESSIONS FOR EXTRACTING FAR SCRAPE-OFF LAYER TRANSPORT COEFFICIENTS FROM THE PLASMA-WALL INTERACTION OF DIVERTOR TOKAMAKS
DOE OSTI已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。
Maintenance strategy, structural design, and site layout of the ST-E1 fusion power plant
DOE OSTI已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。
Turbulent heat transfer for coolant water flow in plasma facing component
Elsevier BV已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。
Power and particle exhaust in the ST-E1 fusion power plant
DOE OSTI已收录公开题录与来源记录，正文内容及使用条件请通过原始发布页面核对。