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Monte Carlo Treatment for Neutral Particle Transport Problems in a Toroidal Plasma

S. Inoue, Y. Taji, Y. Nakahara, T. Suzuki

Nuclear Science and Engineering / Volume 73 / Number 2 / Pages 119-124

February 1980

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Transport of neutral particles in a toroidal plasma is treated in the same manner as that of neutrons by the Monte Carlo method. A new sampling technique of flight-path length is proposed for the torus geometry. Several routines relating to the toroidal geometry have been developed and incorporated into the neutron and gamma-ray transport Monte Carlo code “MORSE.” Results obtained from sample calculations to check the cylindrical approximation show that hot neutrals escape more easily from the torus than from the cylinder, while cold neutrals are retained better in the cylinder. Furthermore, the spectrum of the leakage neutrals is compared with the neutral and ion spectra inside the torus.

 
 
 
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