Published September 2014 | Version v1
Book

Using Tally Values to Add a Third Dimension when Viewing Planar Mesh Tallies - Paper 95

  • 1. White Rock Science, P. O. Box 4729, Los Alamos, NM 87544 (United States)

Description

Mesh tallies show a calculated quantity, such as radiation flux or dose rate, in cells of a rectangular, cylindrical, or spherical mesh. Mesh tallies are useful when the spatial distribution of the quantity is of interest. They are usually displayed in two dimensional (2D) plots with the tally values represented by color coding. Geometry outlines and/or contour lines may be included. Three dimensional (3D) views of rectangular tallies often show a set of tally planes within the geometry. We describe here a new 3D mesh tally plot where the third dimension of a rectangular mesh tally plane is determined by the tally value in each mesh cell. We refer to such plots as elevated mesh tally plots. These plots may aid in analysis and presentation of the results of a transport calculation. The results shown here were calculated with the Monte Carlo transport code MCNPX2.7. The plots were made with the White Rock Science visualization and geometry editing program Moritz. The elevated mesh tally plots have been implemented within Moritz. The elevation method is, at present, only applicable to rectangular mesh tallies. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
ISBN
978-0-89448-714-9
Imprint Pagination
4 p.

Conference

Title
18. Topical Meeting of the Radiation Protection and Shielding Division of ANS
Acronym
RPSD 2014
Dates
14-18 Sep 2014
Place
Knoxville, TN (United States)

INIS

Optional Information

Notes
2 refs.; available on CD Rom from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)