Two incidents involving internal exposure by inhalation of transuranic compounds are presented herein. The results of the measurements of urinary and faecal excretions of the two individuals involved do not concur with the values predicted by the ICRP models that should be applied by default, according to the circumstances of the incidents and the chemical form of the products involved: oxide in the first case and nitrate in the second. These cases are remarkable in the similarity of their biokinetic behaviour even though they occurred in different situations and involved different chemical compounds. Both situations provide an illustration of the management of internal contamination events. The precautions to be taken and the questions that the physician should ask himself in the estimation of the internal dose are listed as follows: What type of examinations should be prescribed and at what frequency? What analysis results should be used in assessing the dose? How can the effect of the Ca-DTPA treatment be assessed? How long is it necessary to perform radiotoxicological exams before assessing the dose? What should be done if the ICRP model corresponding to the initial circumstances does not fit the measurement data? Finally, our selected hypotheses, used to explain specific biokinetic behaviour and to estimate its intake in both cases, are detailed. These incidental contaminations suggest that further studies should be carried out to develop a new model for inhalation of transuranic compounds that would follow neither the S nor the M absorption type of the respiratory tract model of ICRP publication 66.

The radionuclide contents of sediment samples collected from 20 surface-water dams in southwestern Nigeria have been determined by low-level gamma-spectroscopy. The average concentration of 40K in each of the dams varied between 110.9 ± 11.9 Bq kg-1 and 1025.9 ± 36.8 Bq kg-1 with an overall mean (± SD) of 549.3 ± 247.6 Bq kg-1 while that of 238U varied from 17.1 ± 3.6 to 51.9 ± 8.7 Bq kg-1 with an overall mean (± SD) of 27.6 ± 8.5 Bq kg-1 and that of 232Th varied from 26.2 ± 3.6 Bq kg-1 to 130.1 ± 23.7 Bq kg-1 with overall mean (± SD) of 62.0 ± 26.1 Bq kg-1. The variability of the values shows the wide disparity in the measured activity concentrations. The mean radium equivalent of 158.9 Bq kg-1 was calculated for the sediments in the dams. No artificial gamma emitting radionuclide was detected in the samples.

Dans le cadre d’une réflexion sur l’impact environnemental et sanitaire du tritium, un séminaire a été organisé par les experts de l’article 31 du traité Euratom en novembre 2007 à Luxembourg. Son objectif était de préciser les axes de recherches et développement et de déterminer des points réglementaires qui devaient être revus compte tenu de l’évolution des connaissances. Cet article présente les informations relatives aux sources et stocks actuels de tritium, rappelle succinctement les différentes techniques de mesure utilisables en considérant l’ensemble des besoins d’analyses, et présente à grand traits les connaissances principales et les incertitudes associées sur les transferts entre compartiments de la biosphère en conditions normales et accidentelles.

L’article R. 4456-1 du code du travail fait obligation au chef d’établissement de désigner au moins une personne compétente en radioprotection (PCR). Bien que les prérogatives de celle-ci soient exercées sous la responsabilité du chef d’établissement, les règles traditionnelles de mise en cause de la responsabilité s’appliquent aussi bien au chef d’établissement qu’à la PCR. Qu’il s’agisse de la responsabilité civile, dont l’objet est de garantir la réparation d’un dommage par son auteur, ou de la responsabilité pénale, qui vise à sanctionner un comportement répréhensible, la PCR n’échappe pas à ces règles de droit commun qui, toutefois, s’appliquent de manière particulière compte tenu de ses missions quotidiennes. Si la responsabilité de l’employeur est davantage mise en cause, notamment du fait de l’autorité qu’il exerce sur son employé, la PCR ne doit pas être considérée comme irresponsable sur les plans civil et pénal puisqu’elle est susceptible d’être mise en cause par un salarié victime d’un dommage. L’activité de la PCR – et donc les cas permettant l’engagement de sa responsabilité – repose largement sur les moyens dont elle dispose et le contexte dans lequel elle exerce sa mission. Le juge tient d’ailleurs largement compte des ressources dont dispose un agent pour juger de sa responsabilité. Dès lors, les relations de la PCR avec les autres acteurs de la radioprotection, internes ou externes à l’établissement, sont déterminantes.

This article deals with the estimation of inserted defects in bone material by photons used for radiation therapy, for instance, to treat carcinogenic diseases including bone cancer. However, there are side effects by radiation on structures of bones. Structure alters electron density of states that, in time, influences biomedical reactions on bone life condition. Exoelectron emission (EEE) phenomenon underlies a new electron spectroscopy to explore alteration of the electronic structurally dependence properties of bone material. The influence of photons with different energies and the dose rate on the bone structure is discussed. The bone EEE response is not linear on the dose rate and probably is connected with interaction of radiation induced centers responsible for EEE process. EEE structural changes have varied with energy variety of doses used in radiotherapy.

The 11th European ALARA Network (EAN) workshop on “ALARA in radioactive waste management” took place in Athens (Greece) in April 2008. The aim of that workshop was to focus on the implementation of the ALARA principle with regard to occupational and public exposures arising from the management of radioactive waste in all sectors (nuclear, medical, industrial, etc.). This workshop consisted of invited oral presentations, which highlighted the main issues, and half of the programme was devoted to discussions within working groups on specific topics. Individual presentations (papers and slides) are available to download from the EAN website (http://www.eu-alara.net). Based on report backs from the groups and discussions with all the participants, five formal recommendations have been formulated. These recommendations, addressed to international organisations (International Atomic Energy Agency, European Commission, Nuclear Energy Agency), national authorities, national and local stakeholders and to EAN itself, deal with the following themes: international guidance on ALARA in radioactive waste management, harmonisation issues at the international level, ALARA approach in non-nuclear waste management, “broader approach” in the radioactive waste management process, stakeholder involvement. The objective of this paper is to present the main conclusions and the five recommendations produced during the workshop.