Juan Mora - Academia.edu (original) (raw)

Papers by Juan Mora

Presentation of the Radioecology Exchange website

Radioprotection, 2009

The study presented here, being its main goal to evaluate the behaviour of natural radionuclides ... more The study presented here, being its main goal to evaluate the behaviour of natural radionuclides in coal combustion, is part of a wider study carried out by CIEMAT and the University of Extremadura (UEX). The research is addressed to the radiological evaluation of the workers and the public as a result of the operation of the four biggest Spanish Coal-Fired Power Plants (CFPPs). Some generally used effects were confirmed in this study, as the difference in concentration of 210 Po in fly and bottom-ashes. Enrichment factors relative to 40 K as defined by UNSCEAR were found to be a little different than expected. 210 Po enrichment was found in gypsum (material obtained as a by-product in the desulphuration process). In order to confirm the assumption considered to explain difference in 232 Th activity concentration between bottom and fly ashes, carbon content was measured, obtaining that it should be reviewed.

A radiological assessment of the workers and the public potentially affected by the operation of ... more A radiological assessment of the workers and the public potentially affected by the operation of the Teruel Coal-fired Power Plant (the UPT Teruel), was performed under realistic assumptions. This assessment is part of a wider study to characterize the potential radiological impact of Naturally Occurring Radioactive Materials (NORM), in which our team, integrated by University of Extremadura and CIEMAT, is carrying out the study on coal-fired power plants sponsored by the Spanish Nuclear Safety Council (CSN). The study comprises the four biggest coal-fired power plants in Spain. Taking into account the working conditions and the plant specifications, six groups of workers were defined, established considering the 17 working tasks that could be of any importance for this assessment. For the public, considering that the area is barely inhabited, two different recreational scenarios were defined. Therefore, in-plant and outside measurements, needed for the assessment of each scenario, were carried out. Where experimental data were not available or measurements ranged within the natural background radiation values, modelling has been used. Every measured or estimated activity concentration in coal and other used materials or in the by-products generated in the power plant, for every radionuclide in the natural chains of 238 U, 232 Th and 40 K, were below 0.32 Bq g −1 . Those values are under the 0.5 Bq g −1 reference value for exemption and clearance of 238 U, 232 Th and 226 Ra and the 5 Bq g −1 for 40 K recommended in Europe. In the dose evaluations for six groups of workers, a maximum of 21 μSv a −1 was obtained (mainly due to the inhalation of resuspended particles). For both considered scenarios for the public, all the evaluated doses were below 4.3 μSv a −1 . These results are considered negligible from a radiological point of view. In this work the models and assumptions used for the evaluation of workers and public doses, the assessment, as well as the most relevant experimental results and conclusions are presented.

Presentation of the Radioecology Exchange website

Presentation of the Radioecology Exchange website

Radioprotection, 2009

The study presented here, being its main goal to evaluate the behaviour of natural radionuclides ... more The study presented here, being its main goal to evaluate the behaviour of natural radionuclides in coal combustion, is part of a wider study carried out by CIEMAT and the University of Extremadura (UEX). The research is addressed to the radiological evaluation of the workers and the public as a result of the operation of the four biggest Spanish Coal-Fired Power Plants (CFPPs). Some generally used effects were confirmed in this study, as the difference in concentration of 210 Po in fly and bottom-ashes. Enrichment factors relative to 40 K as defined by UNSCEAR were found to be a little different than expected. 210 Po enrichment was found in gypsum (material obtained as a by-product in the desulphuration process). In order to confirm the assumption considered to explain difference in 232 Th activity concentration between bottom and fly ashes, carbon content was measured, obtaining that it should be reviewed.

A radiological assessment of the workers and the public potentially affected by the operation of ... more A radiological assessment of the workers and the public potentially affected by the operation of the Teruel Coal-fired Power Plant (the UPT Teruel), was performed under realistic assumptions. This assessment is part of a wider study to characterize the potential radiological impact of Naturally Occurring Radioactive Materials (NORM), in which our team, integrated by University of Extremadura and CIEMAT, is carrying out the study on coal-fired power plants sponsored by the Spanish Nuclear Safety Council (CSN). The study comprises the four biggest coal-fired power plants in Spain. Taking into account the working conditions and the plant specifications, six groups of workers were defined, established considering the 17 working tasks that could be of any importance for this assessment. For the public, considering that the area is barely inhabited, two different recreational scenarios were defined. Therefore, in-plant and outside measurements, needed for the assessment of each scenario, were carried out. Where experimental data were not available or measurements ranged within the natural background radiation values, modelling has been used. Every measured or estimated activity concentration in coal and other used materials or in the by-products generated in the power plant, for every radionuclide in the natural chains of 238 U, 232 Th and 40 K, were below 0.32 Bq g −1 . Those values are under the 0.5 Bq g −1 reference value for exemption and clearance of 238 U, 232 Th and 226 Ra and the 5 Bq g −1 for 40 K recommended in Europe. In the dose evaluations for six groups of workers, a maximum of 21 μSv a −1 was obtained (mainly due to the inhalation of resuspended particles). For both considered scenarios for the public, all the evaluated doses were below 4.3 μSv a −1 . These results are considered negligible from a radiological point of view. In this work the models and assumptions used for the evaluation of workers and public doses, the assessment, as well as the most relevant experimental results and conclusions are presented.

Presentation of the Radioecology Exchange website