Occurrence of aflatoxin B1 in natural products.

The media claims for the consumption of natural resource-based food have gradually increased in both developing and developed countries. The interest in the safety of these products is partially due to the possible presence of toxigenic fungi acting as mycotoxin producers, such as aflatoxins produced during the secondary metabolism of Aspergillus flavus, A. parasiticus and A. nomius. Aflatoxins, mainly aflatoxin B1, are directly associated with liver cancer in human beings. This paper is aimed at evaluating the presence of aflatoxin B1 in a few vegetable drugs, dried plant extracts and industrialized products traded in 2010 in the city of Belo Horizonte, State of Minas Gerais, Brazil. The method used for the quantification of aflatoxin B1 was based on extraction through acetone:water (85:15), immunoaffinity column purification followed by separation and detection in high efficiency liquid chromatography. Under the conditions of analysis, the Limits of Detection and Quantification were 0.6 µg kg(-1) and 1.0 µg kg(-1) respectively. The complete sets of analyses were carried out in duplicate. Aflatoxin B1 was noticed in a single sample (< 1.0 µg kg(-1)). The results revealed low aflatoxin B1 contamination in the products under analysis. However, it is required to establish a broad monitoring program in order to obtain additional data and check up on the actual extension of contamination.

Tissue distribution evaluation of stealth pH-sensitive liposomal cisplatin versus free cisplatin in Ehrlich tumor-bearing mice.

Multidrug resistance and drug toxicity represent major obstacles to cancer chemotherapy. Drug delivery systems, such as liposomes, offer improved chemical stability of encapsulated drugs, enhanced accumulation in tumors and decreased toxicity. The aim of this study was to evaluate the tissue distribution of stealth pH-sensitive liposomes containing cisplatin (SpHL-CDDP), compared with free cisplatin (CDDP), in solid Ehrlich tumor-bearing mice. After administering a 6 mg/kg single intravenous bolus injection of either free radiolabeled cisplatin or SpHL containing radiolabeled cisplatin, blood and tissues were analyzed for cisplatin content by determining radioactivity using an automatic scintillation apparatus. The area under the CDDP concentration-time curve (AUC) obtained for blood after SpHL-CDDP administration was 2.1 fold larger when compared with free CDDP treatment. The longer circulation of SpHL-CDDP led to a higher tumor AUC, and the determination of the ratio between AUC in each tissue and that in blood (Kp) showed a higher accumulation of CDDP in SpHL-CDDP administrated tumors. The SpHL-CDDP was also significantly uptaken by the liver and spleen. The distribution of SpHL-CDDP in these organs was extensive, revealing a high extravasation of CDDP to the tissues. The SpHL-CDDP kidney uptake was also greater than that of free CDDP; however, the Kp value found was lower. This indicates that the SpHL-CDDP led to a reduction of CDDP retention by renal tissue. Thus, these results indicate that the SpHL-CDDP may indeed be useful in alleviating renal damage induced by CDDP and thus represents a promising delivery system for cancer treatment through CDDP.

An Assessment of the Potential Use of BNNTs for Boron Neutron Capture Therapy.

Currently, nanostructured compounds have been standing out for their optical, mechanical, and chemical features and for the possibilities of manipulation and regulation of complex biological processes. One of these compounds is boron nitride nanotubes (BNNTs), which are a nanostructured material analog to carbon nanotubes, but formed of nitrogen and boron atoms. BNNTs present high thermal stability along with high chemical inertia. Among biological applications, its biocompatibility, cellular uptake, and functionalization potential can be highlighted, in addition to its eased utilization due to its nanometric size and tumor cell internalization. When it comes to new forms of therapy, we can draw attention to boron neutron capture therapy (BNCT), an experimental radiotherapy characterized by a boron-10 isotope carrier inside the target and a thermal neutron beam focused on it. The activation of the boron-10 atom by a neutron generates a lithium atom, a gamma ray, and an alpha particle, which can be used to destroy tumor tissues. The aim of this work was to use BNNTs as a boron-10 carrier for BNCT and to demonstrate its potential. The nanomaterial was characterized through XRD, FTIR, and SEM. The WST-8 assay was performed to confirm the cell viability of BNNTs. The cells treated with BNNTs were irradiated with the neutron beam of a Triga reactor, and the apoptosis caused by the activation of the BNNTs was measured with a calcein AM/propidium iodide test. The results demonstrate that this nanomaterial is a promising candidate for cancer therapy through BNCT.

Production of the radioactive antitumoral cisplatin.

This work presents the preparation of radiolabelled cis-dichlorodiammineplatinum (II), CDDP*, sealed in a cadmium capsule. The irradiation of CDDP covered by cadmium, employing exposure times longer than 2 h, demonstrated good chemical purity and high specific activity. This finding allowed a better detection of in vivo CDDP* and suggests that it may be a good tool for studies of long-term biodistribution of pharmaceutical formulations containing this drug.

Proposed design for the PGAA facility at the TRIGA IPR-R1 research reactor.

BACKGROUND: This work presents an initial proposed design of a Prompt Gamma Activation Analysis (PGAA) facility to be installed at the TRIGA IPR-R1, a 60 years old research reactor of the Centre of Development of Nuclear Technology (CDTN) in Brazil. The basic characteristics of the facility and the results of the neutron flux are presented and discussed. FINDINGS: The proposed design is based on a quasi vertical tube as a neutron guide from the reactor core, inside the reactor pool, 6 m below the room's level where shall be located the rack containing the set sample/detector/shielding. The evaluation of the thermal and epithermal neutron flux in the sample position was done considering the experimental data obtained from a vertical neutron guide, already existent in the reactor, and the simulated model for the facility. METHODS: The experimental determination of the neutron flux was obtained through the standard procedure of using Au monitors in different positions of the vertical tube. In order to validate both, this experiment and calculations of the simulated model, the flux was also determined in different positions in the core used for sample irradiation. The model of the system was developed using the Monte Carlo code MCNP5. CONCLUSION: The preliminary results suggest the possibility of obtaining a beam with minimum thermal flux of magnitude 10(6) cm(-2) s(-1), which confirm the technical feasibility of the installation of PGAA at the TRIGA IPR-R1 reactor. This beam would open new possibilities for enhancing the applications using the reactor.

Occurrence of aflatoxin B1 in natural products

The media claims for the consumption of natural resource-based food have gradually increased in both developing and developed countries. The interest in the safety of these products is partially due to the possible presence of toxigenic fungi acting as mycotoxin producers, such as aflatoxins produced during the secondary metabolism of Aspergillus flavus, A. parasiticus and A. nomius. Aflatoxins, mainly aflatoxin B1, are directly associated with liver cancer in human beings. This paper is aimed at evaluating the presence of aflatoxin B1 in a few vegetable drugs, dried plant extracts and industrialized products traded in 2010 in the city of Belo Horizonte, State of Minas Gerais, Brazil. The method used for the quantification of aflatoxin B1 was based on extraction through acetone:water (85:15), immunoaffinity column purification followed by separation and detection in high efficiency liquid chromatography. Under the conditions of analysis, the Limits of Detection and Quantification were 0.6 µg kg-1 and 1.0 µg kg-1respectively. The complete sets of analyses were carried out in duplicate. Aflatoxin B1 was noticed in a single sample (< 1.0 µg kg-1). The results revealed low aflatoxin B1contamination in the products under analysis. However, it is required to establish a broad monitoring program in order to obtain additional data and check up on the actual extension of contamination.

Influência da irradiação gama na destruição de fumonisina B1 em farinha de milho e de aflatoxina M1 em leite fluido e em pó / Gamma-irradiation effect on fumonisin B1 inactivation in corn flour and on aflatoxin M1 in powdered milk

Fumonisina B1 é a micotoxina produzida por Fusarium verticillioides e Fusarium proliferatum e é encontrada principalmente em milho e produtos a base de milho. Desde sua descoberta a fumonisina B1 tem sido associada a doenças em animais, como leucoencefalomalácia em cavalos e edema pulmonar em suínos. Em humanos, o consumo de alimentos com fumonisina B1 tem sido associado com câncer esofágico. A aflatoxina M1 é o principal metabólito hidroxilado encontrado no leite de animais que consumiram rações contaminadas com aflatoxina B1, bem como no leite de lactantes que consumiram alimentos com esta substância. Neste estudo foi verificado o efeito da irradiação gama (60Co), em doses que variaram de 0 a 20 kGy, quanto à capacidade de inativar fumonisina B1 em farinha de milho e aflatoxina M1 em leite fluido e em pó. A fumonisina B1 foi extraída das amostras com metanol: água(8:2). O extrato foi purificado em coluna de imunoafinidade, seguido de separação e quantificação por meio de cromatografia líquida de alta eficiência (CLAE) com detector de fluorescência, após derivatização com ortoftaldialdeído. Para efetuar a determinação da aflatoxina M1, a amostra foi purificada em coluna de imunoafinidade e a separação e a quantificação por meio de CLAE com detector de fluorescência. Foi observada uma redução da concentração da fumonisina B1 na faixa de 11,2 % a 55,5% em doses de 3 a 20 kGy de irradiação gama (60Co). A concentração de aflatoxina M1 foi reduzida em 86,8 % e 37,9%, respectivamente no leite fluido e em pó, em dose de 20 kGy de radiação.