[en] The nuclear technology, in spite of its big benefits, also has risks and problems. The most pressing is maybe the storage of nuclear waste, for what is not still had a completely satisfactory solution. (Author)

[en] Inside the relative mark to the radioactive waste confinement, minerals of great fixation capacity like clays, apatites and diverse oxides are studied as matrixes, components and/or additives of the active barriers that separate the barrier geologic and the nuclear wastes. In this case, the cements intervene in those different stages of the waste management, since its are used for the immobilization of radioactive waste in the container, for the production of containers as well as filler of the spaces among the containers of the vaults, and also as engineering barrier and construction material in the civil work. For the above mentioned, it is particularly useful to characterize the Portland cements with at least 97% of clinker, since they are most recommended for this type of applications. Presently investigation work is carried out a preliminary chemical characterization, based on the mineralogical composition, of the Portland Mexican cement. Results are shown by the X-ray Diffraction technique when immobilizing a rich solution in sulfates to 5%, using two Portland commercial cements APASCO and TOLTECA, without observing the significant appearance of new phases. The cements besides incorporating the chemical species in the breast of the matrix, are also present as barriers of civil engineering in the facilities located only some meters deep for the storage of radioactive waste of low and intermediate level, for that the study of the radionuclides fixation, in the cements is of supreme importance to evaluate the safety of a nuclear repository with the help of cements; the retention of the iodine-131 in a limited interval of pH in the commercial APASCO and TOLTECA it was studied, being observed a scarce retention of this homologous of fission products, what indicates the necessity to use additives to improve the retention properties of the Mexican commercial cements for some radionuclides. (Author)

[en] The more used isotope at the moment in the services of nuclear medicine in the world is the technetium-99m. The ^99m Tc emitts gamma rays of 141 keV and it semi disintegration period is of six hours, given it short half life, to produce it is necessary to order generators that are systems that allow to separate periodically at the ^99mTc of the ⁹⁹ Mo by means of chromatographic techniques. In this work it is sought to evaluate the use of the hydroxyapatite, to separate molybdates ⁹⁹ MoO₄² of pertechnetates ^99mTcO₄^- and to be able to determine if it is feasible their use for to build generators of ^99m Tc. With this purpose preliminary tests to know the likeness of the hydroxyapatite for the molybdates in function of the pH value, in different solutions were carried out: one of NaCl 0.9%, NaCl 2% and CaCl₂ 0.01 M. The obtained results in a NaCl 0.9% solution and at to 2% to different pH values of the solution, shows that the fixation of the molybdate ions (MoO₄^-2) it is worthless to basic pH values of (9-11), as long as in solution of CaCI₂ 0.01 M show a considerable retention of molybdate ions. (Author)

[en] The demands of materials for the health in the entire world, especially of the odontological and traumatological sectors make every time to be but studied the hydroxyapatite (HAP) and their biocompatibility with the alive beings. The hydroxyapatite is considered as one of the inorganic exchangers by excellence, for what the fixation of ions and molecules have been widely studied and at the moment it is one of the materials of greater acceptance like implant. The surface of the material of implant is in intimate contact with the live tissue and its biocompatibility is determined in great measure by those surface properties of the bio material, which have a direct effect in the cellular response of the material. After administering the implant, the proteins are immediately adsorbed in the surface of the bio mineral. Specifically, the proteins of the blood are considered as key pieces to determine the acceptance of implants in alive beings. The adsorption of proteins it depends on the physicochemical properties of the material as well as of the environment composition. The surface properties of the HAP are relevant in the adsorption mechanisms of the proteins. In this work, it is reported the adsorption of the labelled with I-125 albumin protein and in function of two important physicochemical parameters: the pH value of the of the solution and the chemical nature of the solution; to see the influence of this last, its were studied three electrolytes NaF, NaCl and NaH₂PO₄. The existence of the active sites of hydroxyapatite surface, it is key piece in the interpretation of the fixation of the albumin protein in function also of their acid-base properties. (Author)

[en] It is excessively known the importance about finding a solution for the handling and disposition of radioactive waste of all level. However, the polemic is centered in the administration of high level radioactive waste and the worn out fuel, forgetting that the more important volumes of waste its are generated in the categories of low level wastes or of very low level. Depending on the waste that will be confined and of the costs, several technological modalities of definitive disposition exist, in function of the depth of the confinement. The concept of deep geologic storage, technological option proposed more than 40 years ago, it is a concept of isolation of waste of long half life placed in a deep underground installation dug in geologic formations that are characterized by their high stability and their low flow of underground water. In the last decades, they have registered countless progresses in technical and scientific aspects of the geologic storage, making it a reliable technical solution supported with many years of scientific work carried out by numerous institutions in the entire world. In this work the design concepts that apply some countries for the high level waste disposal that its liberate heat are revised and the different geologic formations that have been considered for the storage of this type of wastes. (Author)

[en] One of the more used techniques for the elimination of the heavy metals present in water systems is to use adsorbent mineral phases like zeolites and clays, among others. The clays are able to exchange easily the fixed ions in the external surface of its crystals or well the ions present in the interlaminar spaces of the structures, for other existent ones in the encircling aqueous solutions for that the Cation exchange capacity (CIC) is defined as the sum of all the cations exchange that a mineral can possess independent to the physicochemical conditions. The CIC is equal to the measure of the total of negative charges of the mineral by mass of the solid (meq/g). In this investigation work, the value of the CIC equal to 2.5 meq/100 g is obtained, of a natural kaolinite from the State of Hidalgo studying the retention of the sodium in the kaolinite with the aid of the radioactive isotope ²⁴ Na and of the selective electrodes technique, making vary the pH value. So is experimentally demonstrated that the CIC is an intrinsic property of the mineral independent of the pH value of the solution and of the charges origin. (Author)

[en] The generator more used in the nuclear medicine it is the generator ⁹⁹ Mo / ⁹⁹ Tc. The separation of ⁹⁹Mo and ^99mTc in the commercial generator is carried out on a column that contains alumina (Al₂0₃). The adsorbent proposed in this investigation work, the hydroxyapatite, is an insoluble solid considered within of the fixers of anions more important. To evaluate the efficiency of the hydroxyapatite in the separation of the Mo and the Tc they were carried out preliminary tests to know the likeness of the one been accustomed to by the molybdate ions (MoO₄^-2) and the pertechnetate ions (Tc0₄^-) in function of the value of the p H, in a solution of CaCI₂ 0.01 M. For the study of the retention of the molybdate ion, it was used the radioisotope Mo-99 fission product, and for the pertechnetate ion it was used the Tc- 99 m radionuclide son of the Mo-99. The obtained results in a solution of CaCl₂ 0.01 M to different values of p H of the solution, show that the fixation of the pertechnetate ions (TcO₄^-) and the fixation of the molybdate ions (MoO₄^-2), they present very different behaviors in the hydroxyapatite. The results indicate that the synthetic hydroxyapatite BIO-RAD retains to the molybdate ion to values of lightly acid p H (5-6), being the retention of the pertechnetate practically worthless. (Author)

[en] With the purpose of knowing the Anion exchange capacity (CIA) of the hydroxyapatite mineral phase, marketed by BIO-RAD, becomes necessary to saturate the surface of the mineral with an anion specie that possesses a strong affinity by this solid as it is the case of the fluorine. Moreover it takes advantage that offers the radioactive tracer technique, using the radioactive isotope of the fluorine, ¹⁸F, produced in the cyclotron of the UNAM. This saturation is obtained in terms of the quantity of retained fluorine (mmol/ 100 g) in the synthetic hydroxyapatite in function of the concentration of the solution of NaF that oscillates from 0.7 M up to 0.16 M to fixed values of pH of 9.2. Those results demonstrate that to this fixed pH value the saturation of the surface of the hydroxyapatite is achieved in approximately 30 mmol/ 100 g, using important concentrations of NaF that correspond to 0.14 M from now on. This result demonstrates the high capacity of the solid considered to retain considerable quantities of fluorine even to basic pH values. (Author)

[en] With the purpose of diminishing the levels of fluorine in the water in certain areas geographical of the country, the interaction of the fluorine is studied, with a Mexican natural clay, called kaolinite and a synthetic apatite called hydroxyapatite. Due to the discharges concentrations of this element in waters of human consumption cause fluorosis dental and osseous, it is important to propose adsorbent materials able to diminish those elevated concentrations of fluorine. In this investigation work the retention of the fluorine is studied in mineral phases using the tracer radioactive ⁸ F. This retention is expressed in terms of the fixed percent of ¹⁸ F, in a natural kaolinite in solution of NaCl 0.01 M, and in a synthetic hydroxyapatite setting in contact with a solution of NaF 0.01 M and a solution of NaH₂PO₄ 0.01 M, all in function of the value of the p H of the solution. The results demonstrate that the influence of the p H is remarkable in the retention of the fluoride in both minerals, demonstrating that the hydroxyapatite (calcium phosphate) it retains in a lot of bigger proportion to the fluorine that the kaolinite (aluminosilicate), all this to values of acid p H, diminishing as the value of the p H increases. (Author)

[en] The ²²⁶ Ra is one of the more radio toxic nuclides since when entering to the organism it continues metabolically to the calcium, accumulating mainly in the bone tissue where it becomes in an internal radiation source. For the analysis of radium in water the methods of radon emanation are generally applied and coprecipitation with barium sulfate. This last is quick and efficient, and the radium in the precipitate can be measured by alpha or gamma spectrometry, or liquid scintillation dissolving the precipitate one with EDTA. In this work it is proposed a procedure for the radium measurement in water based on the coprecipitation with barium sulfate and in the detection by liquid scintillation. The precipitate of Ba(Ra)SO₄ it is carried with water and blended with the liquid scintillator OptiPhase Hi Safe 3, avoiding the dissolution with EDTA. A 92± 1.4% of radium it was recovered and it was reached a minimum activity detectable of 4.2 ± 0.9 mBq^-1. The procedure was essayed with natural mineral water with a knew activity in concentration of ²²⁶ Ra. The analytic result it coincided with the reported value with a relative error of 9%. (Author)