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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.

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