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Practical Calculation of Nuclear Fusion Power for a Toroidal Plasma Device with Magnetic Confinement

机译：磁监禁环形等离子体器件核融合功率的实用计算

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An algorithm has been developed and realized as a FORTRAN code to calculate the volume integral power of a magnetic confinement nuclear fusion reactor and the local fusion rate function. It takes the nuclei energy distributions, fusion cross-sections, and magnetic surface geometry as input data. Two fast, simple analytic models of magnetic flux surfaces were used, and the corresponding Jacobian determinants were found. Gaussian kernel empirical probability density estimation has been proposed to reconstruct the ion energy probability density function from experimentally obtained random samples of escaping neutral atom energies. The influence of ion heating and fast ion confinement on high-energy distribution tails, and thus on the neutron yield and fusion power, can be calculated. The code has been applied to obtain radial profiles of the nuclear fusion reaction rate and volume integral power for both Maxwellian and suprathermal D and T particle distributions. A fast neutral particle diagnostic database may serve as a basis for an experimentally confirmed calculation technique for reactor power and ignition criterion.
机译：已经开发了一种算法，并实现为Fortran代码，以计算磁监管核融合反应堆和局部融合率函数的体积整体功率。它需要核能分布，融合横截面和磁性表面几何形状作为输入数据。使用两个快速，简单的磁通表面的分析模型，并发现了相应的雅可比的决定簇。已经提出了高斯核经验概率密度估计来重建从实验获得的逃逸中性原子能量的随机样品中的离子能量概率密度函数。可以计算离子加热和快速离子限制对高能量分布尾的影响，从而计算中子产量和融合功率。已经应用了代码，以获得核融合反应速率和Maxwerian和Suprathermal D和T粒子分布的核融合反应速率和体积积分功率的径向谱。快速中性粒子诊断数据库可以作为对电抗器功率和点火标准的实验证实计算技术的基础。

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