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Acta Oncol. 2011 Aug;50(6):817-22. doi: 10.3109/0284186X.2011.582516.

Dose determination using alanine detectors in a mixed neutron and gamma field for boron neutron capture therapy of liver malignancies.

Author information

1
Institute for Nuclear Chemistry, University of Mainz, Mainz, Germany. schmito@uni-mainz.de

Abstract

Boron Neutron Capture Therapy for liver malignancies is being investigated at the University of Mainz. One important aim is the set-up of a reliable dosimetry system. Alanine dosimeters have previously been applied for dosimetry of mixed radiation fields in antiproton therapy, and may be suitable for measurements in mixed neutron and gamma fields.

MATERIAL AND METHODS:

Two experiments have been carried out in the thermal column of the TRIGA Mark II reactor at the University of Mainz. Alanine dosimeters have been irradiated in a phantom and in liver tissue.

RESULTS:

For the interpretation and prediction of the dose for each pellet, beside the results of the measurements, calculations with the Monte Carlo code FLUKA are presented here. For the phantom, as well as for the liver tissue, the measured and calculated dose and flux values are in good agreement.

DISCUSSION:

Alanine dosimeters, in combination with flux measurements and Monte Carlo calculations with FLUKA, suggest that it is possible to establish a system for monitoring the dose in a mixed neutron and gamma field for BNCT and other applications in radiotherapy.

PMID:
21767179
DOI:
10.3109/0284186X.2011.582516
[Indexed for MEDLINE]

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