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Calculated neutron dose rates and flux densities from implantable Californium‐252 point and line sources
Author(s) -
Shapiro A.,
Schwartz B.,
Windham J. P.,
Kereiakes J. G.
Publication year - 1976
Publication title -
medical physics
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 1.473
H-Index - 180
eISSN - 2473-4209
pISSN - 0094-2405
DOI - 10.1118/1.594284
Subject(s) - californium , kerma , flux (metallurgy) , monte carlo method , physics , computational physics , line (geometry) , neutron flux , dosimetry , line source , point source , neutron source , neutron , atomic physics , nuclear physics , nuclear medicine , materials science , optics , mathematics , statistics , medicine , geometry , metallurgy
The results of neutron‐transport flux‐density and dose rate calculations for implantable Californium‐252 point and line sources in essentially infinite tissue‐equivalent material are presented. The point‐source flux densities were obtained from a discrete ordinates calculation, and the point dose rates were established by multiplying the flux densities by their appropriate kerma factors. Line‐source dose rates were evaluated by integrating the point dose rates over the length of the line source. Dose‐rate data are given within a 20×20‐cm region from the source center for source lengths of 1.5, 2, and 3 cm. The dose rates established by these calculations showed good agreement with an independent Monte Carlo calculation. Detailed point‐source flux‐density data as a function of energy and position are also given.