发表机构
Lawrence Livermore National Laboratory; Inertia Enterprises（劳伦斯利弗莫尔国家实验室; Inertia Enterprises）
机构由 AI 辅助整理，请以论文原文为准。AI 中文总结
本文基于NIF验证的间接驱动点火物理，提出10 MJ激光驱动的商业聚变靶缩放设计，实现高增益（26-43）和高产额（265-427 MJ），并解决可扩展性、制造及对称性控制等关键问题。
AI 中文摘要
本文介绍了使用10 MJ激光驱动器进行商业相关激光间接驱动（LID）（辐射驱动）惯性聚变能（IFE）的物理基础。迄今为止，这种方法已在国家点火装置（NIF）上得到验证，仍然是第一种也是唯一一种受控聚变方法，能够展示聚变能生产所需的关键物理，包括自持燃烧等离子体，从而大大降低了商业聚变能的路径风险。直接基于这些结果，我们提出了针对更大靶尺寸和商业发电相关聚变增益（$G\sim 26$--$43$）的缩放设计。这些设计保持接近实验验证的点火物理，修改靶组件以提高聚变能应用的可扩展性、可制造性和成本效益，同时保留与点火相关的内爆物理和聚变电厂兼容性。基线平台保留高密度碳烧蚀层和清洁低温DT燃料分层，同时将点火平台扩展到显著更大的燃料质量（超过NIF当前点火实验的10倍）和更高的燃烧份额（$\sim$40%），停滞时的总面密度为$\sim$3~g/cm$^2$。以NIF点火实验为基准的模拟（使用HYDRA和LASNEX）预测，这些设计能实现稳健点火和传播燃烧，聚变产额显著更高（265--427~MJ），并具有显著的点火裕度（相对于NIF为2--4倍），可抵御流体动力学不稳定性和代表性电厂非理想性，包括低模不对称性、多晶DT冰粗糙度、HDC烧蚀层空隙以及靶支撑和充气孔扰动。我们还表明，通过我们使用数千条激光光束线的新型多光束配置，可以控制内爆对称性和激光-等离子体相互作用（LPI）。
英文摘要
This paper presents the physics basis for commercially relevant laser indirect-drive (LID) (radiation-driven) inertial fusion energy (IFE) using a 10 MJ laser driver. To date, this approach, proven at the National Ignition Facility (NIF), remains the first and only controlled fusion method to demonstrate the key physics required for fusion energy production, including a self-sustained burning plasma, substantially de-risking the path to commercial fusion energy. Building directly on these results, we present scaled designs to larger target sizes and fusion gains relevant for commercial power generation ($G\sim 26$--$43$). The designs remain close to experimentally demonstrated ignition physics, modifying target components to improve scalability, manufacturability, and cost-effectiveness for fusion energy applications while preserving ignition-relevant implosion physics and fusion power plant compatibility. The baseline platform retains a high-density carbon ablator and clean cryogenic DT fuel layering while extending ignition platforms to substantially larger fuel masses (exceeding 10 times that of current ignition experiments at the NIF) and higher burn fractions ($\sim$40\%) with total areal densities at stagnation of $\sim$3~g/cm$^2$. Benchmarked simulations anchored to NIF ignition experiments (using HYDRA and LASNEX) predict that these designs achieve robust ignition and propagating burn at substantially higher fusion yields (265--427~MJ) with significant ignition margin (2--4$\times$ relative to NIF) against hydrodynamic instabilities and representative power-plant non-idealities, including low-mode asymmetry, polycrystalline DT ice roughness, HDC ablator voids, and target-support and fill-hole perturbations. We also show that implosion symmetry and laser-plasma interactions (LPI) can be controlled with our novel multi-beam configuration using thousands of laser beam-lines.
CommentsTo be submitted to Physics of Plasmas
