Phantom materials for boron neutron capture therapy.

The aim of this work was to establish which reference phantom material is most suited for dosimetry under reference conditions of neutron beams for boron neutron capture therapy (BNCT). For this purpose, phantoms of dimensions 15 x 15 x 15 cm3 and 30 x 30 x 30 cm3, composed of water, tissue-equivalent (TE) liquid, polyethylene (PE), polymethyl methacrylate (PMMA) and water containing 10 microg g(-1) and 30 microg g(-1) 10B were irradiated using the Petten BNCT beam. Activation foils and a diode detector were used for the determination of the thermal neutron fluence rate. The gamma-ray dose rate and the fast neutron dose rate were determined using paired ionization chambers. In water, PMMA and TE liquid the absolute dose and fluence values agreed within 3% at a reference depth of 2 cm, with the exception of the gamma-ray dose rate in PMMA, which was 12% lower than in water. Due to a higher hydrogen concentration in PE compared with water, the dose and fluence values in PE differed more than 30% from those in water. Only minor differences were observed between the percentage depth dose curves for the various dose components in water, PMMA and TE liquid. The addition of 10 microg g(-1) and 30 microg g(-1) 10B to water resulted in a decrease in the absolute thermal neutron fluence at 2 cm depth of about 2% and 8%, respectively, and a decreased penetration of thermal neutrons at depth for the 30 microg g(-1) 10B concentration. For reference dosimetry of an epithermal neutron beam for BNCT, both water and TE liquid are suitable phantom materials. For practical reasons, water is therefore proposed as reference phantom material. For measurements requiring a solid phantom, PMMA is proposed. The lower gamma-ray dose in PMMA compared to water, however, needs to be taken into account.

A fast and accurate treatment planning method for boron neutron capture therapy.

BACKGROUND AND PURPOSE: The aim of this study was to test the applicability of conventional semi-empirical algorithms for the treatment planning of boron neutron capture therapy (BNCT). MATERIALS AND METHODS: Beam data of a clinical epithermal BNCT beam obtained in a large cuboid water phantom were introduced into a commercial treatment planning system (TPS). For the calculation of thermal neutron fluence distributions, the Gaussian pencil beam model of the electron beam treatment planning algorithm was used. A simple photon beam algorithm was used for the calculation of the gamma-ray and fast neutron dose distribution. The calculated dose and fluence distributions in the central plane of an anthropomorphic head phantom were compared with measurements for various field sizes. The calculation time was less than 1 min. RESULTS: At the normalization point in the head phantom, the absolute dose and fluence values agreed within the measurement uncertainty of approximately 2-3% (1 SD) with those at the same depth in a cuboid phantom of approximately the same size. Excellent agreement of within 2-3% (1 SD) was obtained between measured and calculated relative fluence and dose values on the central beam axis and at most off-axis positions in the head phantom. At positions near the phantom boundaries, generally in low dose regions, local differences of approximately 30% were observed. CONCLUSIONS: A fast and accurate treatment planning method has been developed for BNCT. This is the first treatment planning method that may allow the same interactive optimization procedures for BNCT as applied clinically for conventional radiotherapy.

Dose monitoring for boron neutron capture therapy using a reactor-based epithermal neutron beam.

The aims of this study were (i) to determine the variation with time of the relevant beam parameters of a clinical reactor-based epithermal neutron beam for boron neutron capture therapy (BNCT) and (ii) to test a monitoring system for its applicability to monitor the dose delivered to the dose specification point in a patient treated with BNCT. For this purpose two fission chambers covered with Cd and two GM counters were positioned in the beam-shaping collimator assembly of the epithermal neutron beam. The monitor count rates were compared with in-phanton reference measurements of the thermal neutron fluence rate, the gamma-ray dose rate and the fast neutron dose rate, at a constant reactor power, over a period of 2 years. Differences in beam output, defined as the thermal neutron fluence rate at 2 cm depth in a phantom, of up to 15% were observed between various reactor cycles. A decrease in beam output of about 5% was observed in each reactor cycle. An unacceptable decrease of 50% in beam output due to malfunctioning of the beam filter assembly was detected. For safe and accurate treatment of patients, on-line monitoring of the beam is essential. Using the calibrated monitor system, the standard uncertainty in the total dose at depth due to variations with time of the beam output parameters has been reduced to a clinically acceptable value of 1% (one standard deviation).

The neutron sensitivity of dosimeters applied to boron neutron capture therapy.

To obtain a high accuracy in the dosimetry of an epithermal neutron beam used for boron neutron capture therapy (BNCT), the neutron sensitivity of dosimeters applied to determine the various dose components in-phantom has been investigated. The thermal neutron sensitivity of Mg(Ar) ionization chambers, TE(TE) ionization chambers, and thermoluminescent dosimeters (TLD) has been experimentally determined in a "pure" thermal neutron beam. Values much higher than theoretically expected were obtained and a variation up to a factor of 2.5 was found between values for the thermal neutron sensitivity of different Mg(Ar) ionization chambers of the same type. The sensitivity of the TE(TE) ionization chamber to intermediate and fast neutrons (kt) has been calculated for the neutron energy spectrum in a phantom irradiated by a clinical epithermal BNCT beam, obtained using Monte Carlo simulations. The kt value for muscle tissue ranged from 0.87 at small depths to 0.93 at larger depths in the phantom. The application of the thermal neutron sensitivities to measurements in a phantom irradiated by the epithermal BNCT beam yielded up to 17% higher gamma-ray dose rate values compared with measurements using 6Li containing caps to shield the detectors from thermal neutrons, due to a substantial perturbation of the in-phantom radiation field by the 6Li cap. The application of the new kt values resulted in a dose from intermediate and fast neutrons about 10% higher than the dose based on currently applied relative neutron sensitivities of TE(TE) chambers in BNCT beams. The resulting improvement in the accuracy of the determination of the dose from gamma rays and intermediate and fast neutrons is important in view of the required accuracy for dosimetry in radiotherapy.