The Idaho National Laboratory and the University of Pavia are collaborating in the field of medical neutron dosimetry specific to Neutron Capture Therapy (NCT) applications. This effort resides within a larger framework of computational and experimental dosimetric intercomparisons of several thermal neutron sources used for preclinical NCT radiobiology research worldwide. Recognizing the importance of accurate and reproducible physical beam dosimetry as an essential tool for combination of preclinical and clinical results from different facilities, we have conducted an experimental characterization of the neutronic performance of the thermal neutron source at the University of Pavia TRIGATM research reactor facility. The characterization methodology is based on neutron activation spectrometry coupled with rigorous least-squares-based spectral deconvolution procedures to produce the desired neutron flux, adjusted dosimetry reaction rates, and corresponding radiobiological dosimetric information. Results show that the Pavia neutron source is well thermalized, with a Cadmium Ratio of approximately 80 and a thermal flux of approximately 1 x 1010 n/cm2-s or greater, depending on the specific irradiation location. The submitted poster will discuss further details of the application of advanced modeling and simulation approaches for computational dosimetry of neutron sources, the use of neutron activation spectrometry for experimental validation of research reactor based neutron source performance, and the specific results obtained for the TRIGA facility at Pavia.

Physical Neutron Dosimetry for the University of Pavia Thermal Neutron Source for BNCT Radiobiological Research

PROTTI, NICOLETTA;STELLA, SABRINA;BORTOLUSSI, SILVA;PRATA, MICHELE;ALTIERI, SAVERIO;
2011

Abstract

The Idaho National Laboratory and the University of Pavia are collaborating in the field of medical neutron dosimetry specific to Neutron Capture Therapy (NCT) applications. This effort resides within a larger framework of computational and experimental dosimetric intercomparisons of several thermal neutron sources used for preclinical NCT radiobiology research worldwide. Recognizing the importance of accurate and reproducible physical beam dosimetry as an essential tool for combination of preclinical and clinical results from different facilities, we have conducted an experimental characterization of the neutronic performance of the thermal neutron source at the University of Pavia TRIGATM research reactor facility. The characterization methodology is based on neutron activation spectrometry coupled with rigorous least-squares-based spectral deconvolution procedures to produce the desired neutron flux, adjusted dosimetry reaction rates, and corresponding radiobiological dosimetric information. Results show that the Pavia neutron source is well thermalized, with a Cadmium Ratio of approximately 80 and a thermal flux of approximately 1 x 1010 n/cm2-s or greater, depending on the specific irradiation location. The submitted poster will discuss further details of the application of advanced modeling and simulation approaches for computational dosimetry of neutron sources, the use of neutron activation spectrometry for experimental validation of research reactor based neutron source performance, and the specific results obtained for the TRIGA facility at Pavia.
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/11571/581721
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