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Author Rivard, M. J. ♦ Wierzbicki, J. G. ♦ Van den Heuvel, F. ♦ Martin, R. C. ♦ McMahon, R. R.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword BIOLOGY AND MEDICINE, BASIC STUDIES ♦ CHEMISTRY ♦ DOSIMETRY ♦ NEUTRON DETECTION ♦ CALIFORNIUM ♦ RADIOISOTOPES ♦ RADIOTHERAPY ♦ NEUTRON SOURCES ♦ NEUTRON DOSIMETRY ♦ CALIFORNIUM 252 ♦ MONTE CARLO METHOD ♦ ORNL ♦ ISOTOPE PRODUCTION REACTORS ♦ CALIBRATION ♦ FABRICATION ♦ BRACHYTHERAPY
Abstract Using Monte Carlo methods, neutron dosimetry for {sup 252}Cf Applicator Tube (AT) type medical sources available from Oak Ridge National Laboratory (ORNL) has for the first time been determined in terms of TG-43 formalism. This approach, as compared to previous {open_quotes}along-away{close_quotes} formalisms, demonstrates the relative angular independence of dose rate data, when the geometry factor has been removed. As the ORNL-made {sup 252}Cf AT type sources are considerably physically larger than most clinical sources used today, the radial dose function increases for radii less than 3.0 mm due to breakdown of the line source model. A comparison of the {sup 252}Cf neutron radial dose function with those for other medical sources revealed similarities with that from {sup 137}Cs. Differences with respect to previous {sup 252}Cf AT source neutron dosimetry data generally increased at increasing distances. This was attributed to differences in the various {sup 252}Cf AT source models and phantom compositions. The current status of {sup 252}Cf medical source fabrication and calibration procedures at ORNL is presented. {copyright} {ital 1999 American Association of Physicists in Medicine.}
ISSN 00942405
Educational Use Research
Learning Resource Type Article
Publisher Date 1999-01-01
Publisher Place United States
Journal Medical Physics
Volume Number 26
Issue Number 1


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