A three-dimensional collision probability method: Criticality and neutron flux in a hexahedron setup

Camargo, D. Q. de; Bodmann, B. E. J.; Garcia, R. D. M.; Vilhena, Marco T.

doi:10.1016/j.anucene.2009.03.021

Cited by 2 publications

(2 citation statements)

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“…The collision probability matrix ij p is calculated for all regions that divided into several mesh uses equation (10) of [4]. Equation (1) is inserted to equation (2) to get the k-eff and neutron flux distribution. The iteration is executed for 6…”

Section: Design and Computational Modelmentioning

confidence: 99%

“…For system with simple geometry and symmetrical feature such as cylindrical cell, the neutron transport equation can be solved analytically using the CP method through angular integration. This method is also very efficient for calculating systems with small optical dimensions (i.e., dimensions that are small when expressed in multiples of the mean free path) [2]. In previous work [3] cell homogenization has been predicted numerically using neutron first flight collision probabilities with flat flux (FF) approach.…”

Section: Introductionmentioning

confidence: 99%

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Neutron Distribution in the Nuclear Fuel Cell using Collision Probability Method with Quadratic Flux Approach

Shafii

Fitriyani

Tongkukut

et al. 2017

IOP Conf. Ser.: Mater. Sci. Eng.

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Recent citationsThe Pij matrix and flux calculation of onedimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method Abstract. To solve the integral neutron transport equation using collision probability (CP) method usually requires flat flux (FF) approach. In this research, it has been carried out in the cylindrical nuclear fuel cell with the spatial of mesh with quadratic flux approach. This means that the neutron flux at any region of the nuclear fuel cell is forced to follow the pattern of a quadratic function. The mechanism may be referred to as the process of non-flat flux (NFF) approach. The parameters that calculated in this study are the k-eff and the distribution of neutron flux. The result shows that all parameters are in accordance with the result of SRAC.

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Section: Design and Computational Modelmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%