On a New Point Kernel for Use in Gamma Radiation Calculations

Bindel, Laurent; Gamess, André; Lejeune, E

doi:10.1080/00223131.2000.10874939

Cited by 6 publications

(3 citation statements)

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“…(2) that, for a given solid angle, the integration over s is analytical. As a consequence, the partial contribution to the scalar flux of all possible source points of direction Ω towards the detection point r reads 1 :…”

Section: New Sampling Procedures For the Point Kernel Formulamentioning

confidence: 99%

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A New Point Kernel Sampling Scheme and Monte Carlo Transport

Avez

Bindel

2017

EPJ Web Conf.

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Starting from an existing point kernel intergrated over the bounding surface of a volume source [1], the present contribution proposes a new point kernel sampling scheme. This sampling scheme is shown to be more efficient than the standard one because the integration proceeds from line segment sources instead of point sources. A new kind of Monte Carlo transport process is proposed. It is called flux transport from a line source and is expected to be more efficient than the standard source transport.

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Section: New Sampling Procedures For the Point Kernel Formulamentioning

confidence: 99%

“…(3) was used as an intermediate step to derive Eq. (5) of reference [1]. In a Monte-Carlo evaluation of the integral Eq.…”

Section: New Sampling Procedures For the Point Kernel Formulamentioning

confidence: 99%

A New Point Kernel Sampling Scheme and Monte Carlo Transport

Avez

Bindel

2017

EPJ Web Conf.

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“…When time is an issue, Manuscript for instance, in the generation of dose maps with hundreds of points in industrial facilities, methods based on the point kernel algorithms are usually used. See for instance [4] and [5]. A classic work in dose rate assessment is PUTZ [6].…”

Section: Introductionmentioning

confidence: 99%

Dose rate assessment in complex geometries

Vela¹,

Burgos²,

Pérez³

2006

IEEE Trans. Nucl. Sci.

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A code developed for calculating dose rate maps in scenarios with complex geometries and gamma radiation sources is presented in this work. It is based on the point kernel method. The code computes photon flux and dose rate in preselected positions due to volumetric radioactive sources in the presence of other nonemitting materials acting as shielding. Buildup factors are considered to account for radiation scattering effects, using the Geometric-Progression formula in the fitting function. The major advantage of this code is that there are no constraints for the generation of geometries. Any type and number of volumes can be loaded to generate the scenario by using standard three-dimensional computer-aided design tools. The geometry is imported as a DXF format file. In a second step, material and radiometric attributes are imported for each volume. Volumetric radioactive sources are represented by a set of single emitting point sources distributed within its geometry. The code output has been verified in three different ways: by comparing with results from other point-kernel packages, by comparing with estimates obtained with a Monte Carlo code, and by contrasting with direct experimental measurements. Results of these comparisons are presented and discussed. Finally, intrinsic limitations of the code are discussed.Index Terms-Dose rate calculation, point kernel, three-dimensional (3-D) modeling.

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