252Cf Mixed-Field Dosimetry for a Variety of Source Geometries and Phantom Materials for Clinical Brachytherapy

Comparison of Measurements and Calculations
  • Mark J. Rivard
  • Mark Yudelev
  • Frank Van den Heuvel
  • Jacek G. Wierzbicki
  • Rodger C. Martin
  • Robert R. McMahon

Abstract

The purpose of this study was to compare experimental and calculated mixed-field dosimetry results for 252Cf Applicator Tube (AT) neutron emitting brachytherapy sources. This subject has not been critically examined in many years,1, 2, 3, 4, 5, 6 and is timely as Oak Ridge National Laboratory (ORNL) is now able to fabricate AT sources, and eventually high dose rate (HDR) clinical sources, which would increase availability of high LET radiation sources. 252Cf is unique as it has fast neutrons of relatively low energy and an appreciable photon dose component. Ion chambers and a GM counter were used to measure the total and photon dose, respectively, close to 252Cf AT type sources. A brachytherapy dosimetry protocol was formulated similar to the external beam neutron formalism of ICRU 45. Comparisons of experimental dosimetry were made with results of Colvett et al.4 Neutron kerma in a variety of materials and for various source geometries was calculated using Monte Carlo (MCNP)7 methods and compared with other neutron sources.8

Keywords

Methane Hunt PMMA Protec 

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Copyright information

© Springer Science+Business Media New York 2001

Authors and Affiliations

  • Mark J. Rivard
    • 1
  • Mark Yudelev
    • 2
  • Frank Van den Heuvel
    • 2
  • Jacek G. Wierzbicki
    • 3
  • Rodger C. Martin
    • 4
  • Robert R. McMahon
    • 4
  1. 1.Department of Radiation OncologyTufts University School of Medicine, New England Medical Center #246BostonUSA
  2. 2.Department of Radiation OncologyWayne State UniversityDetroitUSA
  3. 3.Cancer Treatment CenterSaint Mary’s Medical CenterSaginawUSA
  4. 4.Radiochemical Engineering Development Center, Chemical Technology DivisionOak Ridge National LaboratoryOak RidgeUSA

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