Confirmation of a realistic reactor model for BNCT dosimetry at the TRIGA Mainz

Abstract

A computer model for BNCT dosimetry was established, allowing the prediction of dosimetric quantities without further calibration and within a reasonable computation time for clinical applications. The good agreement between the mcnp5 simulations and experiments demonstrates that the attila model overestimates the gamma dose contribution. The detailed model can be used for the planning of structural modifications in the thermal column irradiation channel or the use of different irradiation sites than the thermal column, e.g., the beam tubes.

The alanine detector in BNCT dosimetry: Dose response in thermal and epithermal neutron fields

“…The definition has been extracted from a criticality calculation (see accompanying paper: Confirmation of an elaborate computer model for BNCT dosimetry at the TRIGA Mainz). 30 Source planes at FiR 1 and THOR are circular with a radius of 11 cm. They are located inside the beam collimator close to the beam exit in the case of FiR 1 and at the beam exit at THOR.…”

“…Details of the TRIGA  calculation may be found in the related paper. 30 The measurements at FiR 1 were simulated with the 5 code. The doses in alanine pellets were calculated using the track length estimate tally F4 with the tally multiplier card counting energy deposition in MeV/collision for hydrogen and nitrogen.…”

“…For this paper, data from the previous experiments were recalculated with the enhanced model of the TRIGA Mainz (see accompanying paper: Confirmation of an elaborate computer model for BNCT dosimetry at the TRIGA Mainz). 30 Ten additional pellets have been irradiated in a cuboid-shaped Teflon phantom (8 × 10 × 30 cm). In contrast to PMMA, Teflon contains only carbon and fluorine, but no hydrogen.…”

“…The largest difference between measured values and those calculated with  is 15%, the mean value over 32 pellets is 3%. Values regarding  can be found in the accompanying paper by Ziegner et al 30 Particularly in Figs. 3(b) and 3(c),  superimposes a fluctuation over the monotonically decreasing NPL readouts, which is a result of the statistical uncertainty of 3%.…”

Calculation of BNCT Dosimetry for Brain Cancer Based on Kartini Research Reactor Using Phits Code

“…It is known as a boron dose, which is the main dose delivered to tumor cells or cancer. In addition to the boron dose, other major dose components such as nitrogen doses, gamma doses, and neutron doses are considered in the calculation of BNCT dosimetry [16].…”