From transport to diffusion through a space asymptotic approach

Dulla, Sandra; Canepa, S.; Ravetto, Piero

doi:10.1016/j.matcom.2010.04.007

Cited by 5 publications

(1 citation statement)

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“…El cálculo del coeficiente de difusión puede realizarse de múltiples maneras y constituye toda una teoría en sí mismo (Benoist 1968, Ronen 1987, Dulla, Canepa et al 2010. De modo que su valor dependerá del método utilizado para calcularlo en el código de transporte utilizado para la generación de los parámetros neutrónicos.…”

Section: La Aproximación De Difusión En Estado Estacionariounclassified

Métodos avanzados multiescala núcleo-celdas en geometrías tridimensionales y multigrupos para el cálculo de Reactores de Agua Ligera

Carrascosa¹

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Advanced multi-scale pin-by-pin/core methods in three-dimensional geometries and multigroups for Light Water Reactors calculationsThe relevance of safety in the use of nuclear technology impregnates all the tasks associated to the use of this energy source, beginning with the design phase, exploitation and subsequent dismantling or waste management.In all these steps, computational simulation tools play an essential role as a guide for design, operation supporting or prediction of the reactor materials isotopic evolution.Constant improvements in computational resources from the middle of the 20 th century to this moment as well as the developments in the calculation methods employed, allow tackling the complexity of these situations with greater detail, when this was simply discarded before because of a lack of computational capacity or adequate tools.Present work is centered in the development of a neutronics calculation method for light water reactors based on corrected diffusion theory with a detail to the level of the fuel pin, considering a number of energy groups higher than the traditional fast and thermal groups, and modeling the three-dimensional geometry of the reactor core.

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Section: La Aproximación De Difusión En Estado Estacionariounclassified