17 research outputs found

    The role of glutathione and cysteine conjugates in the nephrotoxicity of o-xylene in rats

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    Moderate nephrotoxicity was induced in male and female rats exposed to o-xylene for 4 h at atmospheric concentrations of approximately 3000 ppm. The xylene in vivo nephrotoxicity resulted in low enzyme leakage from the kidney into the urine. This low leakage was confirmed in 24-h urine by an increase in gamma-glutamyltranspeptidase (gammaGT), N-acetyl-beta-D-glucosaminidase (NAG) and alkaline phosphatase (ALP) activities. Compared to the control, both the 24-h urine output and the glucose excretion increased in male and female rats. These increases were probably a result of damage to the renal proximal tubules. The role of the metabolic pathway of glutathione in the emergence of the renal damage observed with o-xylene was investigated in rats. Recent studies indicate that the metabolic pathway of glutathione may be a bioactivation pathway, which is responsible for nephrotoxic effects with several drugs or chemicals. The renal toxicity of three synthesized o-xylene thio-conjugates was investigated in several groups of female rats. Administration of S-(o-methylbenzyl)glutathione (i.p., 1 mmol/kg), S-(o-methylbenzyl)cysteine (per os, 1 mmol/kg) or N-acetyl-S-(o-methylbenzyl)cysteine (i.p., 0.75 mmol/kg) to female rats did not induce renal toxicity, as monitored by urinary biochemical parameters (gammaGT, NAG, ALP, glucose). The data obtained suggest that the glutathione pathway would appear to be only detoxication, and probably does not contribute to the renal toxicity of o-xylene in female rats. Thus, either another metabolic pathway or other intermediate metabolites are probably involved in the nephrotoxic action of o-xylene

    Metrological characterization of intense (α, n) neutron sources by coupling of non-destructive measurements

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    International audienceMetrological non-destructive characterization of intense (, n) neutron sources (emission rate between 107 and 3108 s−1 into 4 sr solid angle) is a challenge for nuclear applications. In this article, we will present the design, development and in situ validation of two measurement cells especially dedicated to this characterization. The main goal consists in determining the absolute neutron emission rate of this type of neutron sources with relative uncertainties less than 5% (k=1). Another purpose is related to the qualitative and quantitative analysis of fission products present in irradiated neutron sources. Because of experimental constraints, acquisitions were carried out underwater which required a full remote control of the measurement cells. Neutron emission rate is assessed using three different non-destructive techniques: (i) global neutron counting, (ii) neutron activation using gold dosimeters and (iii) gamma-ray spectrometry. We will successively present the design step and associated constraints, main characteristics of measurement cells and associated laboratory characterization as well as experimental results obtained during the final in situ measurement campaign. The latter shows an excellent agreement regarding the neutron emission rate values provided by the three different non-destructive techniques and a relative combined standard uncertainty less than 5% (k=1) for the investigated neutron sources

    Results of the EURAMET.RI(II)- S7.Sm-151 supplementary comparison (EURAMET Project 1292)

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    An international comparison of the activity standardisation of the relatively long-lived gamma-ray emitter 151Sm has been recently completed. A total of six laboratories measured a solution prepared by CEA/LNHB and CEA/LANIE. Aliquots of the master solution were standardized in terms of activity per mass unit by participant laboratories using 2 different techniques. The results of the comparison can be used as the basis for establishing equivalence among the laboratories. The activity measurements of this comparison are part of the joint research project “Metrology for Radioactive Waste Management” of the European Metrology Research Programme (EMRP). One aim of this project is a new determination of the 151Sm half-life.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard
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