Boron Neutron Capture Therapy (BNCT) is a two-step cancer treatment therapy comprising (a) selective accumulation of B into tumor cells using appropriate pharmacological agents and (b) irradiation with thermal neutron. The dosimetric technique described in this paper and the experimental results presented and discussed is based on electron spin resonance (ESR) detectors using an alanine-boric compound acid enriched with (10)B, and beryllium oxide thermoluminescent (TL) detectors; with this combined dosimetry, it is possible to discriminate the doses due to thermal neutrons and gamma radiation in a mixed field. Irradiations were carried out inside the thermal column of a TRIGA MARK II water-pool-type research nuclear reactor, also used for Boron Neutron Capture Therapy applications, with thermal neutron fluence from 10(9) to 10(14) nth cm(-2). The ESR dosimeters using the alanine-boron compound indicated Electron Spin Resonance signals about 30-fold stronger than those using only alanine. Moreover, a negligible correction for the gamma contribution, measured with thermoluminescent detectors, almost insensitive to thermal neutrons, was necessary. Therefore, a simultaneous analysis of the combined TL and B-alanine ESR detectors described in this paper is a valid method for discriminated accurately between thermal neutron and gamma doses in a mixed field, as required in Boron Neutron Capture Therapy.

Combined TL and 10B-alanine ESR dosimetry for BNCT

BORIO, Rita;FORINI, Nevio;SALVADORI, Paolo;
2004

Abstract

Boron Neutron Capture Therapy (BNCT) is a two-step cancer treatment therapy comprising (a) selective accumulation of B into tumor cells using appropriate pharmacological agents and (b) irradiation with thermal neutron. The dosimetric technique described in this paper and the experimental results presented and discussed is based on electron spin resonance (ESR) detectors using an alanine-boric compound acid enriched with (10)B, and beryllium oxide thermoluminescent (TL) detectors; with this combined dosimetry, it is possible to discriminate the doses due to thermal neutrons and gamma radiation in a mixed field. Irradiations were carried out inside the thermal column of a TRIGA MARK II water-pool-type research nuclear reactor, also used for Boron Neutron Capture Therapy applications, with thermal neutron fluence from 10(9) to 10(14) nth cm(-2). The ESR dosimeters using the alanine-boron compound indicated Electron Spin Resonance signals about 30-fold stronger than those using only alanine. Moreover, a negligible correction for the gamma contribution, measured with thermoluminescent detectors, almost insensitive to thermal neutrons, was necessary. Therefore, a simultaneous analysis of the combined TL and B-alanine ESR detectors described in this paper is a valid method for discriminated accurately between thermal neutron and gamma doses in a mixed field, as required in Boron Neutron Capture Therapy.
2004
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11391/151145
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