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Serpent is a continuous-energy Monte Carlo reactor physics code capable for highly detailed, three-dimensional burnup calculation. It is under current development at VTT Technical Research Centre of Finland since 2004 under the original name of "Probabilistic Scattering Game". The code was originally developed with two-dimensional lattice physics calculations in mind; however, the code provides that the geometry can be generally expanded to three-dimensions. The Serpent code makes use of an energy-grid restructuring of cross-sections and delta-ray tracking for speed increases during the neutron transport simulation. The Serpent code is often used for generating cross-sections for deterministic reactor physics codes. ==See also== * Nuclear reactor * Nuclear engineering * Neutron transport * Nuclear reactor physics * Monte Carlo N-Particle Transport Code 抄文引用元・出典: フリー百科事典『 ウィキペディア（Wikipedia）』 ■ウィキペディアで「Serpent (software)」の詳細全文を読む スポンサード リンク
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