Scale and serpent two-group cross-section data generation

Acta Polytechnica CTU Proceedings(2018)

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摘要
In this work, VVER fuel assembly is calculated using two different codes - Serpent and SCALE. Multiplication factor and several two-group macroscopic parameters including scattering cross-section, fission cross-section, total cross-section and diffusion coefficient were studied. In addition to this, fuel isotopic composition dependency on burnup was calculated as a part of this study. Obtained data are compared and differences are discussed. Both codes provides similar results for all studied parameters.
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关键词
VVER, Serpent, VVANTAGE-6, fuel cycle, burnup, SCALE, Temelin nuclear power plant, depletion calculation, homogenized cross-sections
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