Uranium In Urine Samples Research Articles

Measurements of uranium in urine samples of uranium workers and inhabitants of nearby settlements in Akmola Region, Kazakhstan

The main purpose is determine and evaluate uranium concentration in urine of the inhabitants of nearby settlement of uranium mining sites and workers of uranium processing sites. As uranium enterprises working in Stepnogorsk of Akmola Region and its exploitation could be a risk of radiation exposure for the workers as well as for the local population, monitoring of biosamples could allow information about the exposure to uranium for the workers and inhabitants. Workers and inhabitants of male genders were asked to collect 24 h-urine samples. The concentration of uranium in urine was measured in mass spectrometry (ICP-MS). Uranium concentration in urine samples from workers values ranged from 0.05 to 12.5 μgL−1 , for Akmola region inhabitants values ranged from 0.10 to 0.60 μgL−1 . The results of concentrations of uranium in the urine of inhabitants living near SMCC were comparable to values reported in other studies. The concentration of uranium in the urine of the workers had slightly elevated values, comparable to the conditional norm of 0.9 μg/L.

Uranium Concentrations in Urine of Maternal Samples in Baghdad Governorate

The trace concentration of uranium in urine samples for pregnant women and non- pregnant women were determined using fission track technique with CR-39 track detector that is employed for registration of induced fission tracks. A total of 32 urine samples were collected from Yarmouk Teaching Hospital, Department of Obstetrics and Gynecology for Pregnant women and 5 urine samples were collected from Different regions of Baghdad governorate. The results show that the uranium concentration in urine of Pregnant women were ranged from 0.58 μg/l (30 years old, living in AL- Shurta AL khamisa region) to 1.58 μg/l (23 years old living in AL–Doura region) with average 0.92±0.2 μg/l. While for non-Pregnant women, uranium concentration ranged from 0.61 μg/l (24 years old, living in AL-Doura region) to 1.16μg/l (40 years old, living in AL-Ghazaliya region) with average 0.874±0.19μg/l. It was found that the average uranium concentrations in urine samples for pregnant women living in Hayi AL-maealif region higher than other regions in Baghdad governorate.

Assessment of Uranium in Urine Samples of Primary School Students

The environmental monitoring of radon in the children urine has been carried out by using solid state nuclear track detector CR-39. This study has been undertaken for the purpose of health risk assessments. The concentration of uranium values excreted with the boy's urine samples ranged from 0.203 Bq.L-1 (1.246 ng/L) and 2.201 Bq.L-1 (13.486 ng/L) with an average value of 0.698 Bq.L-1 (4.007 ng/L). While the concentration of uranium values excreted with the girl's urine samples ranged between 0.290 Bq.L-1 (1.777 ng/L) and 0.675 Bq.L-1 (4.135 ng/L), with an average value of 0.474 Bq.L-1 (2.901 ng/L). The amount of uranium deposited in the kidneys, according to ICRP's biokinetic model, and the annual radiation dose were also calculated. All values of the study samples were within the normal range and do not indicate any health hazard.

Rapid analysis technique for strontium, thorium, and uranium in urine samples

Rapid analysis for 90Sr, 232Th, and 238U in human urine samples collected in a radiation emergency can be developed by co-precipitation with calcium phosphate and separation using a Sr-resin (Eichrom Technologies, Inc.) column. The nuclides were measured by inductively coupled plasma mass spectrometry (ICP-MS) or a low background β-counter. Spike tests yielded a good recovery of above 90%. Fractions of 90Sr and the other nuclides (232Th and 238U) were separated in about 2 hours. It was judged that the developed method would be an effective bioassay method in radiation emergency.

A normative value pilot study: Levels of uranium in urine samples from UK civilians

A normative study of the levels of urinary uranium in the general UK population is needed for comparison with levels in UK military and ex-military personnel who served where munitions containing depleted uranium (DU) were used. As preparation, this pilot study trialled the process of collecting 24-h samples from adult male civilians, and compared the measurements from 24-h samples with those from spot samples taken over the subsequent 24 h. The purpose was to assess the relative utility of the two types of samples. Twenty-five convalescent hospital in-patients were recruited as participants. Uranium concentrations in the 24-h samples ranged from 1 to 10.6 ng l −1; in the spots, from not detectable to 38.1 ng l −1. Normalised to creatinine, concentrations in the 24 h samples ranged from approximately 100 to 800 ng mol −1 creatinine; in the spot samples, from not detectable to approximately 4000 ng mol −1 creatinine. The ranges appear similar to those reported for residents of the US. The distribution of spot sample results indicated that 95% of a participant's creatinine-adjusted concentrations from spot samples would be within the range 40–250% of his mean. Adjusting for creatinine almost entirely eliminated a slight indication of diurnal variation in urinary uranium concentration in spot samples. All the 24-h samples and 131 out of the 133 spot samples showed ratios of isotopes 238U to 235U consistent with natural uranium (i.e. neither enriched nor depleted). Slightly elevated ratios in two spot samples were not supported by other samples from the same participants, indicating that slightly elevated ratios may be recorded on very low concentration (<1 ng l −1) samples. In the main, quantification of this isotope ratio from spot samples was only slightly more variable than from 24-h samples. Complete 24-h urine samples gave better precision than spot samples in estimating uranium concentrations at these low levels, but presented more logistic difficulties in the collection of the samples. Clarification of the relative merits of alternative sampling strategies enables the design of a wider study to be optimised.

Uranium bioassay and radioactive dust measurements at some uranium processing sites in Egypt--health effects.

The safety of radiation workers in the uranium mining industry requires close and continuous monitoring of their working conditions. In this study, external radiation surveillance, radioactive dust monitoring and the bioassay of uranium were carried out in some processing sites. As dust represents one of the most important sources of radiation exposure in mills and mines, dust monitoring and bioassays were performed for a sample of workers on the production lines. The concentration of uranium in air ranged from 22.6 x 10(-7) to 11.1 x 10(-5) Bq cm-3, and the exposure levels ranged from 1 to 80 microSv h-1. Laser fluorimetric determination of uranium in urine samples showed concentrations in the range 8.4-29.2 micrograms L-1. Renal function parameters, such as serum creatinine and urea, and hematological parameters were determined in an attempt to correlate them with radiation exposure and the health status of the workers. Urine specimens collected from workers at the ore crushing and separation site showed elevated concentrations of uranium (up to 29.2 micrograms L-1) and a strong correlation between these concentrations and the registered serum creatinine. The mean uranium excretion in the investigated group was more than 20 times the occupational exposure decision level for urine uranium of 0.8 microgram L-1.

STUDY OF WORKER'S EXPOSURE TO THORIUM, URANIUM AND NIOBIUM MINERAL DUST

The aim of this study is to evaluate worker’s exposure to particles, with special attention to thorium, uranium and niobiumbearing particles. A cascade impactor (CI) with six stages was used to collect particles with aerodynamic diameter in the rangeof 0.64 to 19.4 μm. The elemental mass concentrations impacted in each stage of the CI were determined using the PIXE(Particle Induced X-ray Emission) technique. The Mass Median Aerodynamic Diameter (MMAD) and elemental mass concentration in the fine fraction of aerosol (0.5 to 2.5 μm) were determined.Personal air samplers were used by workers to collect fine particles of aerosol. The concentrations of 232Th and 228Th in these air samplers were measured by the alpha spectrometry technique. Faeces and urine samples from the workersand their wives were analyzed to determine the thorium, uranium and niobium mass concentration (mass spectrometry) and 232Th, 228Th, 238U and 234U concentrations (α spectrometry) and then compared to inhabitants of regions with low metal concentrations. The analysis of thefaecesand urine samples from workers and their wives indicated that themain pathway of thorium, uranium and niobium incorporation was byingestion. The observed concentrations of niobium and uranium inurine samples from workers showed a systemic incorporation of niobium and uranium.

Optimal sample preparation conditions for the determination of uranium in biological samples by kinetic phosphorescence analysis (KPA).

Kinetic phosphorescence analysis (KPA) is a proven technique for rapid, precise, and accurate determination of uranium in aqueous solutions. Uranium analysis of biological samples require dry-ashing in a muffle furnace between 400 and 600 degrees C followed by wet-ashing with concentrated nitric acid and hydrogen peroxide to digest the organic component in the sample that interferes with uranium determination by KPA. The optimal dry-ashing temperature was determined to be 450 degrees C. At dry-ashing temperatures greater than 450 degrees C, uranium loss was attributed to vaporization. High temperatures also caused increased background values that were attributed to uranium leaching from the glass vials. Dry-ashing temperatures less than 450 degrees C result in the samples needing additional wet-ashing steps. The recovery of uranium in urine samples was 99.2+/-4.02% between spiked concentrations of 1.98-1980 ng (0.198-198 microg l(-1)) uranium, whereas the recovery in whole blood was 89.9+/-7.33% between the same spiked concentrations. The limit of quantification in which uranium in urine and blood could be accurately measured above the background was determined to be 0.05 and 0.6 microg l(-1), respectively.

Determination of uranium in urine samples of fuel element fabrication workers by beta-delayed neutron counting

Within the health physics examination of fuel element fabrication workers, the control of uranium incorporation is of importance. This is commonly performed by the determination of the alpha activity concentration of uranium excreted in the urine. However, since the chemical separation procedure and the preparation of alpha-counting samples are complicated and time-consuming, this method may imply restrictions on the routine control of large numbers of persons. Therefore, we have investigated the applicability of measuring the beta-delayed neutrons from thermal neutron induced fission of the 235U in the urine samples. The uranium was separated by coprecipitation with Fe(OH) 3 from the urine samples and irradiated in a rabbit system of the Mainz TRIGA reactor. The neutrons were counted with a 3He long counter. The detection limit of 0.3 to 0.9 pCi 1 −1 is comparable to that of alpha spectrometry, but the time required for one sample, from preparation to data evaluation is less than 25 min.