Sample records for caldasite

  1. Uranium leaching analysis (IAEA method) and total uranium determination in caldasite by the fluorometric method

    International Nuclear Information System (INIS)

    Sardela, I.A.; Fujimori, K.


    Caldasite is a radioactive mineral known mostly for its high radioactive content (U and Th). It is found only at the Pocos de Caldas Alkaline Complex, States of Minas Gerais. Samples colected at Campos do Serrote, Taquari and Brigrada located in the alkaline complex were submitted to the fluorometric method of uranium analysis. The results show a good precision and close agreement with those obtained with gamma ray spectroscopy. IAEA uranium leaching analysis has also been applied to this mineral, but only 0,4% of the total content was dissolved. The uranium leaching was more intense on the samples that have smaller equivalent uranium than total uranium and it may be attributed to a higher range Rn gas escape from this mineral. (Author) [pt

  2. Optimization of the caldasite processing conditions by alcaline melting

    International Nuclear Information System (INIS)

    Brown, A.E.P.


    A study has been done to recover economically the uranium and zirconium values of the ores at Pocos de Caldas Plateau in the state of Minas Gerais, Brazil. In a preliminar study, it was investigated the opening of the ore by alcaline fusion that were carried out in a temperature controlled furnace and the variables studied were the time, temperature and NaOH/ore ratio. The optimization procedure was based on the steepest Ascent Method developed by Box and Wilson, utilizing a complete 2 3 factorial design. The analysis of the data indicated the response optimum for the process in: time 1.52 +-0.1 hour; temperature 805 +-15degC; NaOH/ore ratio 1.7 ton/ton. Solubilizations higher than 97%ZrO 2 and recuperations nearly of 100%U 3 O 8 are obtained arouns this point [pt

  3. Aerial monitoring in the caldasite chrorination pilot plant

    International Nuclear Information System (INIS)

    Goncalez, O.L.


    The results of air monitoration in the chlorination facility of the PMR/IPD/CTA are presented. The total dust and alpha activity concentration in the air were measured in two representative work places. Two common type of anti-dust masks were evaluated. The samples were taken by air aspiration by a plane membrane filter. It was found that both total dust and alpha activity concentrations are lower than the maximum permissible levels. (Author) [pt

  4. <報文>レアメタル資源に関する研究(I) : ジルコニウム資源としてのPocos de Caldas, Brasil産カルダサイト


    佐藤, 修彰; 伊藤, 良雅; 南條, 道夫


    The zirconium deposit of the Pocos de Caldas Plateau is north of Sa^^?o Paulo, Brasil, on the boundary between the States of Minas Gerais and Sa^^?o Paulo. The zirconium ore was formed as a mixture of baddeleyite (ZrO_2) and zircon (ZrSiO_4) which was identified as caldasite from the microscopic, X-ray and electron microprobe studies. This ore also contained a high content of uranium and thorium oxides, enough for nuclear fuel resources from the γ-ray spectrometry. The ore shows stable behavi...

  5. Development and Building of Radioactive Concrete Pads for calibration of the airborne and ground gamma-ray spectrometers, used in mineral exploration and hydrocarbons

    International Nuclear Information System (INIS)

    Carlos, Dionisio Uendro


    Eight transportable calibration pads were built in to be used as concentration standards for portable and airborne gamma-ray spectrometers calibrations. The pads construction procedure is described in full detail. The pads, with dimensions of 1 m x 1 m x 0,30 m and masses between 593 kg and 673 kg were made radioactive by the addition of different amounts of k-feldspar, caldasite and monazitic sand to the concrete masses. The potassium, uranium and thorium concentration vary significantly in the pads, reaching maximum values of 5,7% of K, 45,6 ppm eU and 137 ppm eTh. The distribution of the gamma radiation flux from the pads surfaces and the heterogeneity magnitudes of the radioactive elements concentration were experimentally established. An example of gamma-ray spectrometer calibration is presented. (author)

  6. Spectrophotometric determination of uranium and thorium with arsenazo III in the flow injection system

    International Nuclear Information System (INIS)

    Andrade, M. das G.M. de.


    A simple system for flow injection analysis (FIA) with double confluence was built using a filter photocolorimeter, an analogic potentiometer, 'plexiglass' flow cuvettes, polyethylene colls and tubes, 'plexiglass' commuter and peristaltic pump to introduce solutions and gravity as flow source. The system was dimensioned and studied using only Arsenazo III solutions. Spectrophotometric methods for uranium and thorium using Arsenazo III were studied using a scanning spectrophotometer and after chosing adequate red filter, adapted to photocolorimetry using flow cuvettes and FIA. Synthetic samples, phosphate rock, and process samples from uranium recovery of dolomites were analysed. Rocks of Morro do Ferro (MG, Brazil), Caldasite (Baddeleyte + Zirconite), Zirconite, Monazite from a program for certification and certified rocks (Dunite DC-1, CANMET) were analysed without chemical separation of Th (IV) and with ion exchange separation in semi-micro columns of cation exchange resin (Dowex 50). (Author) [pt

  7. Development of method for quantification of 222Rn exhalation ratio at radioactive waste dam and soil study as mitigator material

    International Nuclear Information System (INIS)

    Macacini, Jose Flavio


    The Brazilian uranium mining company (INB) processed 2.32 10 6 tons of uranium ore in its ore treatment unit (UTM - Caldas), located in the Pocos de Caldas plateau. During 16 years of operation, this unit discarded 2.39 10 6 tons of solid waste in a tailing dam, with an average activity concentration of 226 Ra of 7311 ± 184 Bq kg -1 . Most of the atoms of 222 Rn generated from the radioactive waste of the tailing dam remain bounded to the mineral structure. However, a fraction of these atoms can be released from the mineral structure and then emanate. Reaching the porous space of the waste piles, the 222 Rn moves towards the interface waste-atmosphere, exhaling into the atmosphere. The featuring properties of the 222 Rn transport and the biological damage caused by its progeny transform this small chain of radionuclides into a scourge of nature. Because of that, the dry area of the tailing dam was the scope of this work. A methodology was developed for quantifying the exhalation rate of 222 Rn. Moreover, the soil from its surroundings was experimentally evaluated as a cover material to reduce the exhalation of 222 Rn. A collector of 222 Rn was developed, being denominated 607. This collector was proved to be exact and precise after laboratory tests, when a standard for 222 Rn exhalation was prepared with caldasite, an uranium ore with high concentration of 226 Ra (26611 ± 581 Bq kg -1 ), crushed to the granulometric interval from 1.168 mm to 0.589 mm. The results of 222 Rn exhalation rate using the collector 607 were not influenced by the adsorption of water steam, considering sampling periods lower than 5 days and mass of water steam lower than 7 g. Sampling for measuring 222 Rn exhalation rates in the dry area of the tailing dam was carried out using the collector 607, following the experimental design established by the United States Environmental Protection Agency (US EPA). The average exhalation rate in the west part of the tailing dam was 1.30 ± 1.24 Bq m