RESUMEN
The evaluation of possible improvement in the use of Gd in cancer therapy, in reference to gadolinium in cancer therapy (GdNCT), has been analysed. At first the problem of the gadolinium compounds toxicity was reviewed identifying the Motexafin Gadolinium as the best. Afterwards, the spectrum of IC and Auger electrons was calculated using a special method. Afterwards, this electron source has been used as input of the PENELOPE code and the energy deposit in DNA was well defined. Taking into account that the electron yield and energy distribution are related to the neutron beam spectrum and intensity, the shaping assembly architecture was optimised through computational investigations. Finally the study of GdNCT was performed from two different points of view: macrodosimetry using MCNPX, with calculation of absorbed doses both in tumour and healthy tissues, and microdosimetry using PENELOPE, with the determination of electron RBE through the energy deposit. The equivalent doses were determined combining these two kinds of data, introducing specific figures of merit to be used in treatment planning system (TPS). According to these results, the GdNCT appears to be a fairly possible tumour therapy.
Asunto(s)
Gadolinio/uso terapéutico , Neoplasias/radioterapia , Terapia por Captura de Neutrón/métodos , Fármacos Sensibilizantes a Radiaciones/uso terapéutico , Gadolinio/farmacocinética , Gadolinio/toxicidad , Humanos , Isótopos/farmacocinética , Isótopos/uso terapéutico , Isótopos/toxicidad , Método de Montecarlo , Terapia por Captura de Neutrón/estadística & datos numéricos , Terapia por Captura de Neutrón/tendencias , Fármacos Sensibilizantes a Radiaciones/farmacocinética , Fármacos Sensibilizantes a Radiaciones/toxicidad , Planificación de la Radioterapia Asistida por Computador/estadística & datos numéricosRESUMEN
Monte Carlo numerical calculations of the response of alanine and ammonium tartrate ESR (electron spin resonance) dosimeters exposed to neutron fields with different energy spectra are reported. Results have been obtained for various gadolinium concentrations inside the dosimeters. Furthermore, in order to simulate the in-phantom response we have carried out calculations by varying the depth of the dosimeter. We have found that a large enhancement is obtained for thermal neutrons, because of the very high capture cross section of gadolinium to thermal neutrons. A good enhancement was obtained for epithermal neutrons, whereas the sensitivity improvement in the case of fast neutron irradiation is poor. Furthermore, the simulations carried out by varying the depth suggests that an appreciable sensitivity to thermal and epithermal neutrons could be observed for in-phantom measurements in the 2-3 cm depth range. These results can provide useful insight for future experiments with epithermal neutron beams (such as those used in neutron capture therapy) and for future applications in neutron capture therapy dosimetry.
Asunto(s)
Espectroscopía de Resonancia por Spin del Electrón/estadística & datos numéricos , Gadolinio/uso terapéutico , Terapia por Captura de Neutrón/estadística & datos numéricos , Radiometría/estadística & datos numéricos , Planificación de la Radioterapia Asistida por Computador/estadística & datos numéricos , Alanina , Neutrones Rápidos/uso terapéutico , Humanos , Método de Montecarlo , Fantasmas de Imagen/estadística & datos numéricos , TartratosRESUMEN
The purpose of the work was to build a prompt gamma neutron activation analysis (PGNAA) facility at the MEPhI reactor for analyzing the content of various elements for NCT. The facility was implemented on a monochromatic neutron beam. Methods of quantitative (10)B and Gd measurement have been developed for pharmacokinetic studies. The facility is capable of measuring 1 microg of (10)B and 10 microg of Gd in biological samples with an error less than 10%. The detection limit of the facility is 0.3 microg of (10)B and 2 microg of Gd. Neutron flux attenuation within biological tissue samples was estimated and a new system for determining the elemental concentration was suggested.
Asunto(s)
Boro/análisis , Gadolinio/análisis , Análisis de Activación de Neutrones/instrumentación , Animales , Boro/farmacocinética , Boro/uso terapéutico , Terapia por Captura de Neutrón de Boro/estadística & datos numéricos , Gadolinio/farmacocinética , Gadolinio/uso terapéutico , Rayos gamma , Humanos , Isótopos/análisis , Isótopos/farmacocinética , Isótopos/uso terapéutico , Ratones , Análisis de Activación de Neutrones/estadística & datos numéricos , Terapia por Captura de Neutrón/estadística & datos numéricos , Reactores Nucleares , Federación de Rusia , Distribución TisularRESUMEN
PURPOSE: Cell survival assays were performed to evaluate the effects of radiations released during neutron capture reactions by gadolinium-157, boron-10 and by the combination of both. MATERIALS AND METHODS: Single cell suspensions with or without Gd-157 and/or B-10 were exposed to thermal neutrons produced by the Kyoto University reactor, and standard cell survival curves were obtained. RESULTS: Under the same molarity, cytocidal effects were 1.5 times greater for Gd-157 than for boron when compared at 10% survival levels. The presence of B-10 enhanced the radiation effect of Gd-157 neutron capture by 1.2-fold, suggesting that cells were not sufficiently irradiated as a result of neutron fluency attenuation by the presence of excess neutron capture agents in the medium. CONCLUSIONS: When an equal number of atoms were present, Gd-157 was effective as B-10 when exposed to an equal number of thermal neutrons. However, there was no benefit observed in the combination of Gd-157 and B-10 for neutron capture therapy. Further studies are needed to determine optimal Gd-157 and B-10 concentrations as a function of tumor dimension.
Asunto(s)
Boro/uso terapéutico , Gadolinio/uso terapéutico , Terapia por Captura de Neutrón/métodos , Neutrones/uso terapéutico , Radioisótopos/uso terapéutico , Animales , Supervivencia Celular/efectos de la radiación , Células Cultivadas , Cricetinae , Cricetulus , Terapia por Captura de Neutrón/estadística & datos numéricosRESUMEN
The development of capillary neutron optics permits a new technology for neutron capture therapy involving the application of a focused thermal neutron beam at the medically optimal location within the patient. A subthermal neutron beam begins to converge as it travels through a neutron "lens," reaching a narrow focus within a tube that allows it to pass directly to the treatment region. This technique results in a substantially lower dose to untreated parts of the patient and a substantially weaker radiation field in the treatment room generally. Additional advantages include the relative ease of thermal neutron generation and the ability to shield the patient completely and effectively from fast neutrons or gamma rays originating at the neutron source. This work describes the application of capillary optics to neutron capture therapy, along with Monte Carlo calculations of the neutron flux profiles within a patient for an optimized system design. Specific dose profiles for the case of boron neutron capture therapy within the brain are also provided.