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Di Giorgio M.,Autoridad Regulatoria Nuclear ARN | Vallerga M.B.,Autoridad Regulatoria Nuclear ARN | Radl A.,Autoridad Regulatoria Nuclear ARN | Taja M.R.,Autoridad Regulatoria Nuclear ARN | And 16 more authors.
Radiation Protection Dosimetry | Year: 2013

The bottleneck in data acquisition during biological dosimetry based on a dicentric assay is the need to score dicentrics in a large number of lymphocytes. One way to increase the capacity of a given laboratory is to use the ability of skilled operators from other laboratories. This can be done using image analysis systems and distributing images all around the world. Two exercises were conducted to test the efficiency of such an approach involving 10 laboratories. During the first exercise (E1), the participant laboratories analysed the same images derived from cells exposed to 0.5 and 3 Gy; 100 images were sent to all participants for both doses. Whatever the dose, only about half of the cells were complete with well-spread metaphases suitable for analysis. A coefficient of variation (CV) on the standard deviation of ̃15 % was obtained for both doses. The trueness was better for 3 Gy (0.6 %) than for 0.5 Gy (37.8 %). The number of estimated doses classified as satisfactory according to the z-score was 3 at 0.5 Gy and 8 at 3 Gy for 10 dose estimations. In the second exercise, an emergency situation was tested, each laboratory was required to score a different set of 50 images in 2 d extracted from 500 downloaded images derived from cells exposed to 0.5 Gy. Then the remaining 450 images had to be scored within a week. Using 50 different images, the CVon the estimated doses (79.2 %) was not as good as in E1, probably associated to a lower number of cells analysed (50 vs. 100) or from the fact that laboratories analysed a different set of images. The trueness for the dose was better after scoring 500 cells (22.5 %) than after 50 cells (26.8 %). For the 10 dose estimations, the number of doses classified as satisfactory according to the z-score was 9, for both 50 and 500 cells. Overall, the results obtained support the feasibility of networking using electronically transmitted images. However, before its implementation some issues should be elucidated, such as the number and resolution of the images to be sent, and the harmonisation of the scoring criteria. Additionally, a global website able to be used for the different regional networks, like Share Points, will be desirable to facilitate worldwide communication © The Author 2012. Published by Oxford University Press. All rights reserved. Source


Bedregal P.S.,Instituto Peruano Of Energia Nuclear Ipen | Mendoza P.A.,Instituto Peruano Of Energia Nuclear Ipen | Ubillus M.S.,Instituto Peruano Of Energia Nuclear Ipen | Yepez W.,Proyecto Coleccion Arqueologica La Real | And 2 more authors.
Journal of Radioanalytical and Nuclear Chemistry | Year: 2015

Fragments of archaeological pottery from a rescue excavation at the site of La Real in Arequipa, Peru, were studied by instrumental neutron activation analysis, k0 method. Analytical data were processed by multivariate statistical techniques, comparing the chemical composition of the studied samples versus the information available in our database on the chemical composition of archaeological pottery from Conchopata (Ayacucho), Cotahuasi (Arequipa), Huaro (Cusco) and Tiwanaku (Bolivia). The results obtained revealed that most of the samples were likely made locally at La Real, while others correspond to the chemical composition of the different groups considered, showing evidence of the presence of foreign pottery in the site and a small group which were not classified. © 2015, Akadémiai Kiadó, Budapest, Hungary. Source


Blanco S.,CONICET | Mora P.,Research Center en Ciencias Atomicas | Almonte N.,Direccion Nuclear | Benavente T.,Instituto Peruano Of Energia Nuclear Ipen | And 11 more authors.
Radiation Protection Dosimetry | Year: 2013

The International Atomic Energy Agency (IAEA) through the International Action Plan on Radiation Protection of Patients and the International Commission on Radiological Protection have for some time carried out important efforts to assure that in the medical applications of the ionising radiations, the optimisation of radiological protection of patients is fundamental, to such a point that the IAEA includes it directly as a requirement for these practices (in its International Basic Safety Standards for Protection against Ionising Radiation and for the Safety of Radiation Sources (BSS)-GSR Part 1, 2011). For this reason, among the objectives of Regional Project RLA/9/057 and Regional Project RLA/9/067, the intention was to establish the dose references in conventional radiology for Latin America, for the purposes of determining whether these doses comply with the requirements of the BSS and to tend to improve practices, in order to minimise the dose received by the patients. © The Author 2013. Published by Oxford University Press. All rights reserved. Source


Bedregal P.S.,Instituto Peruano Of Energia Nuclear Ipen | Mendoza P.A.,Instituto Peruano Of Energia Nuclear Ipen | Ubillus M.S.,Instituto Peruano Of Energia Nuclear Ipen | Yepez W.,Proyecto Coleccion Arqueologica La Real | And 2 more authors.
Journal of Radioanalytical and Nuclear Chemistry | Year: 2015

Fragments of archaeological pottery from a rescue excavation at the site of La Real in Arequipa, Peru, were studied by instrumental neutron activation analysis, k0 method. Analytical data were processed by multivariate statistical techniques, comparing the chemical composition of the studied samples versus the information available in our database on the chemical composition of archaeological pottery from Conchopata (Ayacucho), Cotahuasi (Arequipa), Huaro (Cusco) and Tiwanaku (Bolivia). The results obtained revealed that most of the samples were likely made locally at La Real, while others correspond to the chemical composition of the different groups considered, showing evidence of the presence of foreign pottery in the site and a small group which were not classified. © 2015 Akadémiai Kiadó, Budapest, Hungary Source


Mora M.V.,Instituto Peruano Of Energia Nuclear Ipen | Padilla A.G.,Instituto Peruano Of Energia Nuclear Ipen | Palomino J.L.C.,Instituto Peruano Of Energia Nuclear Ipen | Terremoto L.A.A.,Brazilian Nuclear Engineering Institute (IEN)
Progress in Nuclear Energy | Year: 2011

Gamma-ray spectroscopy is an important nondestructive method for the qualification of irradiated nuclear fuels. Regarding research reactors, the main parameter required in the scope of such qualification is the average burnup of spent fuel elements. This work describes the measurement, using nondestructive gamma-ray spectroscopy, of the average burnup attained by Material Testing Reactor (MTR) fuel elements irradiated in the RP-10 research reactor. Measurements were performed at the reactor storage pool area using 137Cs as the only burnup monitor, even for spent fuel elements with cooling times much shorter than two years. The experimental apparatus was previously calibrated in efficiency to obtain absolute average burnup values, which were compared against corresponding ones furnished by reactor physics calculations. The mean deviation between both values amounts to 6%. © 2011 Elsevier Ltd. All rights reserved. Source

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