Les objectifs de la dosimétrie individuelle sont multiples ; leur hiérarchisation a sensiblement évolué au cours des dix dernières années : l'optimisation s'est peu à peu imposée comme un objectifmajeur de la radioprotection des travailleurs. Les limites maximales admissibles vont être abaissées d'un facteur important. Les objectifs dosimétriques que se donnent les exploitants sontégalement fortement réduits année après année. Les situations d'exposition sont très diverses selon les secteurs d'activité. Les nouveaux procédés technologiques ont entraîné autant denouveaux champs de rayonnements avec des spectres et niveaux de dose variés. Aucun détecteur ne répond parfaitement pour l'ensemble des champs de rayonnements rencontrés. Pour lesphotons, tous les dosimètres existants et utilisés en routine permettent l'évaluation de Hp(10) selon les spécifications des normes. Pour les neutrons, aucune technique existante ne satisfait lesnormes. 
Les informations complémentaires offertes par certains dosimètres peuvent entrer en ligne de compte dans le choix d'une technique plutôt qu'une autre. Les contraintes techniques et financièresvarient selon les solutions : un service dosimétrique complet comprend le dosimètre mais aussi son système d'exploitation et de gestion. L'exploitation des dosimètres passifs diffèrecomplètement de celle des dosimètres actifs. Des procédures de validation des résultats doivent être imaginées dans le deuxième cas, en particulier les dosimètres actifs fournissent une masseimportante de données dont il faudra sélectionner et valider certaines avant de les enregistrer dans un système de gestion centralisé. Les techniques évoluent, en particulier celles basées surl'électronique : les techniques d'intégration permettent d'envisager raisonnablement dans un avenir de 3 à 5 ans la mise au point de dosimètres combinant les différentes fonctions : x, g , b etneutron, mesure en temps réel. La réglementation devrait être suffisamment souple pour permettre aux utilisateurs de choisir au mieux la technique adaptée à leur besoin et laisser la possibilité deprendre en compte l'évolution à venir des techniques.

Two types of plants (lettuce and radish) were contaminated by dry deposition of radioactive aerosols (137Cs, 85Sr, 133Ba and 123mTe). Due to the rain efficiency in decreasing radiological contamination of crops, a rain scenario was applied on the two types of plants. These experiments aimed at improving the prediction of the consequences on agricultural products of a nuclear accident occurring on a PWR, and at improving the understanding of the different processes occurring between contamination and harvest. For a plant species at a given stage of its growth cycle, the interception of the four radionuclides was found to be identical and varied from 68% for radish to 75% (at the middle of ripeness stage) or 78% (at the mature plant stage). Using a conceptual model, the predominance between the two processes - washing-off the leaves and absorption through the leaves cuticles allowing translocation - was evidenced. For Cs, Sr and Ba, for both the lettuce and the radish, washing-off on the foliar cover was the most significant during the first rain. The absorption process inside the plant became dominant only from the third rain event. Tellurium had a particular behaviour: it was non-mobile and stayed put on the leaves. The values of the washing-off and absorption coefficients were estimated. The global transfer factor values were dependant on both the radionuclides and the plant species; nevertheless, a higher value was obtained for cesium, regardless of the plant and the rainfall (from 0.06 m2.kg$_{\scriptsize\textrm{fresh}}$-1 for radish to 0.1 m2.kg$_{\scriptsize\textrm{fresh}}$-1 for a whole lettuce).

In 2003 IAEA launched the EMRAS Programme aiming at evaluating the predictive power of radiological models. The programme continued work of previous international radioecological modelling programmes and comprised several working groups focusing on different aspects of environmental modelling. The Iodine Working Group reassessed the impact of the release of 131I during the Chernobyl accident with the aim of comparing model predictions with environmental data and inter-comparing the model predictions. Measurement data and detailed geographic and demographic descriptions were available for three regions: Plavsk, Warsaw and Prague. As for the Prague Scenario, milk supply regions of three big dairies were chosen for the model validation. Apart from geographic, demographic and agricultural descriptions (e.g. gathering regions of the dairies, feeding regime), the modellers were provided with information on the weather conditions and measurement data of iodine contamination. The most important peculiarities of Prague Scenario were keeping milk cattle in sheds and a special feeding regime during May 1986. The modellers were asked to assess the 131I content in the thyroid of the local population and the resulting dose. The assessments were compared with measurement data. The results of these model calculations and their comparison with experimental data are presented.

Pour l'homme, le radon est la source permanente principale d'exposition naturelle aux rayonnements ionisants. Ce document synthétise les connaissances générales sur l'origine du radon 222 et son évolution dans différents milieux atmosphériques. Il présente diverses méthodes de mesure de l'activité volumique radon et de la concentration, en énergie alpha potentielle de ses descendants à vie courte. Il a été élaboré dans le cadre de la commission M60-3 du Bureau de Normalisation d'Équipements Nucléaires (BNEN) qui dépend de l'Association Française de Normalisation (AFNOR).

The uranium isotopes 238U, 235U and 234U are foundnaturally in the environment. 238U and 235U are parent nuclides of twoindependent decay series of isotopes, while 234U is a member of the238U decay chain. When decay series occur in a closed system the series tendsto reach, with time, the state of secular equilibrium in which the activities of all seriesmembers are equal to the activity of its first nuclide. The activity ratio234U/238U in natural uranium may vary as a consequence of decaychain disequilibrium due to alpha recoil and biogeochemical processes. A study based onmeasurement of uranium concentration and 234U/238U activity ratios insoil samples collected from Nalgonda district, Andhra Pradesh, India, a proposed miningsite, was carried out to find the spatial distribution of uranium and the state of secularequilibrium of 234U/238U to examine the possibility of applyinguranium concentration and uranium isotopic activity ratios to detect any hydrogeochemicalchanges in the environment during/post-operation. Soil samples were collected and analyzedfor uranium concentration using the conventional UV fluorimetric method, showing a uraniumconcentration in the range of 0.7 ± 0.2 ppm to 7.9 ± 0.4 ppm with an average of 3.4 ppm, and234U/238U activity ratios were estimated using the alphaspectrometry technique, showing an activity ratio in the range of 0.92 ± 0.11 to1.02 ± 0.11. The 234U/ 238U activity ratio obtained indicated thatthese two uranium isotopes are in the state of secular radioactive equilibrium. The percentactivity ratio of 238U/total U and 234U /total U is observed to varyfrom 47.94 ± 4.83 to 50.76 ± 4.87 and 45.80 ± 3.83 to 49.14 ± 3.99, respectively.

La directive européenne 2006/25/CE, relative à l'expositiondes travailleurs aux rayonnements optiques, prévoit l'évaluationdes risques des situations de travail. Elle est particulièrementimportante dans l’industrie des arts du spectacle où des expositionsintentionnelles à des projecteurs peuvent être exigées pendant despériodes de l’ordre de 8 heures par jour. L'objectif de la présenteétude était de fournir aux éclairagistes des informations, relativesaux risques associés aux projecteurs, afin de les aider à évaluerles risques a priori d’un plan lumière. Elle aconsisté à déterminer les risques de 63 projecteurs différents puisà les répartir dans les 4 groupes de risques définis par la normeEN 62471, à calculer leur distance minimale d’exposition admissible,correspondant à l’utilisation de 1 et de 5 projecteurs pour unedurée d’exposition journalière de 8 heures. Cette étude a mis enévidence que les projecteurs sont susceptibles de poser des problèmessanitaires pour les salariés des arts du spectacle. Le schéma de classificationproposé par la norme EN 62471 n'est pas suffisant pour évaluer lesrisques d'un plan lumière. De plus, la distance d'exposition etla durée d'exposition ne constituent pas des paramètres pertinentspour réduire les risques à des valeurs admissibles.

Objectif : déterminer l’intérêt des gants radio-atténuateurs plombés pour diminuerl’exposition des mains des opérateurs, en radiologie interventionnelle et au blocopératoire. Matériel et méthode : on a utilisé des gants radio-atténuateurs plombés dumarché, des dosimètres TLD thermoluminescents, un fantôme anthropomorphe de calibration enostéodensitométrie, une main anthropomorphe. Les mesures étaient réalisées sur 2installations : l’une avec capteurs plans, l’autre avec amplificateur de brillance. On acomparé les doses reçues par dosimètres sans et dans un gant, dans le champ direct (10séries de mesures dont 2 avec amplificateur de brillance) et dans le diffusé (3 séries surcapteurs plans), en scopie et graphie. Résultats : dans le diffusé, les dosimètres dans legant mesuraient une diminution de dose, variant de 1 à 3. Dans le champ direct, 7 mesuressur 10 montraient une augmentation de dose dans le gant (13 à 42 %). 3/10 mesuresmontraient une quasi stabilité de dose avec le gant (–3,3 % à  +2 %). Conclusion : nosmesures objectivent une efficacité des gants radio-atténuateurs plombés dans le diffusé.Dans le rayonnement direct, le port des gants radio-atténuateurs plombés entraîne uneaugmentation de la dose – main, du fait des réglages automatiques des paramètres.

Three sediment cores were sampled at Sepetiba bay and four cores at Ribeira bay, Rio de Janeiro State, Brazil. Sedimentation rates were determined applying 210Pb dating. In the Ribeira Bay, the sedimentation rate increases in the direction from sampling point RB1 (0.15 cm y-1), in the inner part of the bay, to 0.34 cm y-1 in the sampling point RB4, close to its entrance. For the Sepetiba Bay, two sedimentation rates were observed: a lower rate of 0.3 cm y-1, for the period before the 60's, and a more recent rate of 0.75 cm y-1. These findings agree with the construction of the Santa Cecília impoundment (1955) that brings water from the Paraíba do Sul Basin into the Guandu River, increasing its flow from the original 20 m3 s-1 to 160 m3 s-1. In order to determine the elemental concentrations, aliquot from the SB1 and RB4 cores were taken, totally dissolved and analyzed by ICP-MS. The hypothesis that Ribeira Bay could constitute a reference database for metal concentrations in the neighboring Sepetiba Bay is valid for several elements as K, Ti, Mn, Zn, Ga, Rb, Sr among others, but it isn't for other elements as V, Cr and Cd. Applying to the mean elemental concentration, of the upper contaminated 45 cm sediment layer, and to the elemental concentration of the deepest analyzed sediment layer a normalization to iron, a double ratio was calculated and it was concluded that the Sepetiba Bay sediments are, particularly, contaminated with Cr, may be, from a leather tanning plant existing in this region and Cd and Zn from the former Ingá Metais.

A low cost in-situ gamma-ray spectrometric method for rapid assessment of radiation exposure, identification of radionuclides and detection of changes in environmental radioactivity has been employed in the determination of the natural gamma radiation dose levels in six major cities of the southeastern region of Nigeria. The soil radioactivity concentrations of the primordial radionuclides; 40K, 238U and 232Th were determined and have been related to the γ-dose rates in the cities. The activity concentration of 40K across the region ranged between 0.021 and 0.200 kBq kg–1; 238U was between 0.001 and 0.066 kBq kg–1 while that of 232Th ranged between 0.015 and 0.103 kBq kg–1. The total γ-absorbed dose rates in air in the region ranged between 0.016 and 0.090 μGy h–1 with a mean of 0.039 ± 0.018 μGy h–1. The mean of the annual outdoor effective dose due to the terrestrial gamma radiation for the region was calculated as 50 μSv y–1 representing 66% of the world average value.

In this paper our current knowledge of the mechanisms underlying the induction of bystander effects by low dose low LET ionizing radiation is reviewed in the context of relevance to radiation protection issues. The question of how bystander effects may be related to observed adaptive responses, systemic genomic instability or other effects of low doses exposures is also considered. Bystander effects appear to be the result of a generalized stress response in tissues or cells. The signals may be produced by all exposed cells, but the response may require additional system parameters to exist in order to be expressed. The major response involving low LET radiation exposure discussed in the existing literature is a death response. This can manifest as apoptotic cell death, terminal differentiation, reproductive cell death or necrosis. While a death response might appear to be adverse, the position is argued in this paper, that it can in fact be protective and remove damaged cells from the reproducing population. Since many cell populations carry damaged cells without being exposed to radiation (so-called “background damage”), it is possible that low dose radiation exposures cause removal of cells damaged by agents other than the test dose of radiation. This mechanism would lead to the production of “u- or n-shaped” dose response curves. In this scenario, the level of harmful or beneficial response will be related to the background damage carried by the cell population and the genetic program determining response to damage. This model may be particularly important when attempting to predict the consequences of mixed exposures involving radiation and other environmental stressors on biota.

Les problèmes de la dosimétrie dans les champs de rayonnements ionisants diffusés autour des accélérateurs de haute énergie sont présentés. Après une courte introduction sur l'historique des grandeurs physiques utilisées pourl'acquisition de l'équivalent de dose, les techniques diverses pour la dosimétrie dans des champs mixtes à haute énergie sont décrites, en commençant par des mesures spectrales compliquées, puis par la présentation des moyens en multidétecteurs et en instruments sur la base des détecteurs proportionnels. Enfin l'utilisation de méthodes simples est mise en évidence pour le cas où l'on dispose d'une connaissance initiale et supplémentaire sur la composition des rayonnements ionisants. Il est montré que les résultats des mesures correspondent bien à ceux obtenus à l'aide des programmes de calcul modernes.

La directive 97/43/EURATOM du 30 juin 1997 pointe laradiologie interventionnelle comme une des pratiques spéciales (Article9) susceptibles de délivrer des doses élevées, et pour lesquellesil est demandé de veiller à ce que les équipements, les procédures,les programmes d’assurance qualité et la formation des opérateurssoient particulièrement appropriées. En effet, l’utilisation d’unrayonnement X de faible énergie lors de procédures allant de quelquessecondes à plusieurs heures pour les examens complexes, renvoie inévitablementà des risques stochastiques et déterministes. L’évaluation de ladose maximum à la peau est donc une donnée appréciable dans l’objectifd’un suivi dermatologique du patient. Dans cette étude nous avonschoisi d’utiliser comme détecteur les films radiochromiques XR-RV3-Gafchromic®afin d’obtenir une cartographie de la dose à la peaureçue par le patient lors d’une procédure. Les films radiochromiquessont intéressants car ils permettent à la fois de visualiser etde quantifier la région de dose maximale. Nous présentons ici les étapespréliminaires à une utilisation sur patient des films, à savoirl’étude des caractéristiques physiques, l’étalonnage en dose, lalecture par scanner plat et l’exploitation des films avec le logicielde traitement d’images ImageJ. Les résultats obtenus montrent quel’utilisation des films radiochromiques est pertinente pour uneévaluation dosimétrique sur patient. Plus particulièrement, la réponsedes films diffère de moins de 3,6 % entre l’étalonnage à 80 kV et120 kV et l’incertitude globale reste inférieure à 20 % jusqu’àune dose de 12 Gy. L’évolution de la réponse du film dans le tempsétant négligeable, la lecture peut être faite immédiatement et l’exploitationdu film nécessite moins de 15 minutes pour obtenir la cartographiede la dose. L’application de cette technique de mesure in-vivo pour 58procédures a permis de mettre en évidence une dose maximale à lapeau supérieure à 3 Gy pour 12 patients. Ces patients ont alorsété orientés vers un suivi dermatologique. Parmi ces patients, l’évaluationde la dose peau à partir des indicateurs dosimétriques fournis parl’installation aurait mené au suivi de seulement 4 patients.

For appropriate safety assessment of TRU waste disposal, gasification ratios and distribution coefficients (Kd) of 14C labeled [1, 2-14C] sodium acetate were determined by batch experiments for a Japanese paddy soil sample. Approximately 60% of the total added C-14 was released from the flooded paddy soil into the air as gas forms during 7 days shake-incubation periods. In the present study, the paddy soil was contacted with deionized water and well water, and the lower gasification ratio was found for the well water sample. The similar result was observed for the Kd values. Values of Kd varied from 51 to 138 mL g-1. The lower values were observed when the soil was contacted with well water. When the microorganisms in the samples were killed by glutaraldehyde, both gasification ratios and Kd values were nearly zero. These results suggested that microorganisms responsible for the behavior of C-14 in biosphere. In addition, water characteristics such as dissolved ions, pH and electrical conductivity would affect the gasification ratio and the Kd values.

The dosimetric consequences of 14C dissemination resulting from the radioactive fall-out of atmospheric nuclear-weapons testing conducted in the 50s have been estimated. Owing to the lack of 14C measurements in food consumed in France over the past 60 years, this evaluation is based on the standard modelling of the isotopic equilibrium: it is assumed that the specific activity (14C/C) of living plants is in equilibrium with that of CO2 in the air. It is also considered that this isotopic ratio remains constant in animals and their production. The specific activities of 14C in the biosphere were drawn from reference publications. Since the 1950s, the effective dose for adults has risen from 12.1 µSv y-1 to a maximum of about 22.3 µSv y-1 in 1964, before falling to 12.9 µSv y-1, which is slightly higher than the initial value. The excess dose due to atmospheric testing reached about 10 µSv y-1 in the sixties. The generation of 1940 was exposed to the highest dose: 190 µSv in 60 years due to nuclear-weapons testing, which remains low in relation to natural exposure.

Des résultats de mesures de tritium libre et organiquement lié ont été acquis de 2007 à 2012, en France métropolitaine, pour des échantillons de végétaux et de denrées prélevés en milieu terrestre, hors de l’influence potentielle d’un rejet. Le bruit de fond, déduit de ces données, n’évolue pas significativement; il est en moyenne de 1,4 ± 1,2 Bq/L pour le tritium libre et pour le tritium organiquement lié.

Contemporary open source JAVA technologies implemented within the EURANOS project for thecross-platform re-engineering of the decision support system RODOS (JRODOS) were used alsoto redesign the Hydrological Dispersion Module (HDM) of this system. JHDM – thehydrological model chain of JRODOS contains models to simulate the radionuclide transportin the system “atmospheric fallout on watershed – river net” and calculate the doses viaaquatic pathways. JHDM used for this purpose a limited number of the input parameters tocharacterize the hydrological properties of the catchment/river network of interest. Thepilot implementation of JHDM for the Vistula river basin carried out by POLATOM andsupported by the national hydrological institute, demonstrated good perspectives of theapproach used in JHDM for the decision support in cases of accidental contamination ofwater systems. Particular needs for further improvements of the JHDM software system havebeen identified.

In estuaries, volatiles radionucleides (14C, 3H, 131I) originating from anthropogenic liquid waste release from nuclear reactor or hospitals are potentially transferable to the atmosphere. Due to the high biologic activity, the degradation of organic matter produce carbon dioxide fluxes to the atmosphere allowing transfer of 14CO2 released by nuclear industry. Similarly tritium is transfered to the atmosphere trough evaporation process. We present here, results obtained during FLORE-1 cruise in February 2003, a winter period when biological activity is supposed to be low. The first results of iodine 131 distribution and estimations of radiocarbon and tritium fluxes are presented.

Assessments of natural gamma radiation were done for urban sites in the city of Ribeirão Preto – SP – Brazil, allowing to infer the average annual effective dose value for the population in these areas. The measurements were done using a vehicle with a mobile radioactivity measurement system, Eberline, with a plastic scintillation detector and a Global Position System (GPS), to collect measurements of gamma dose rate and its spatial distribution. Using the national census information, the stored data allowed mapping the radiometric measurements through the ArcGIS software, correlating the geographical coordinates with their respective dose rates. These maps illustrate how effective dose values are distributed within the selected areas and also correlate the collective dose values for these populations. Around 45,000 georeferenced effective dose values, ranging from 12.2 up to 59.8 nSv/h raised an average value of 0.034 ± 0.004 mSv/year, which is less than the worldwide average effective dose value of 0.07 mSv/year [12] (for outdoor exposures from terrestrial radiation sources) and less than the previous average values found in Brazil for the regions of Poços de Caldas, Guarapari, Andradas, Caldas and Meaípe [2,10].

Pinus sylvestris L. populations growing at the territory affected by nuclear waste storage facilities were monitored in 1997-2002. Cytogenetic damage levels within root meristem of seedlings significantly exceed corresponding controls. Populations experiencing man-caused influence have a higher seeds radioresistance and enlarged cytogenetic variance. These are considered as an indication of adaptation processes in the studied pine populations. An analysis of the structure of ecological-genetical variability is carried out. Changes of two components of the intrapopulational variance were studied in dependence on time and man-caused impact. The first component is engaged to the genetically determined variability of biological characteristics intrinsic for the species and is dominant in studied tree populations. The second is responsible for the variance originating from anthropogenic contamination of the natural habitat. A tendency of destabilizing dynamics and increasing mean values of intraclass correlation coefficient that is a measure of contribution from heterogeneity among trees into total cytogenetical variability is demonstrated under conditions of chronicle technogenic impact on pine populations.

It is important to obtain local transfer factors (TFs) of long-lived radionuclides for assessment of radioactive waste disposal, because climates, soil types and vegetation can affect TFs. Global fallout 90Sr and 137Cs are good tracers to obtain the TFs under natural conditions, however, their radioactivity levels in plants are extremely low. To close the gap, analyses of stable isotopes and natural radioisotopes in rice and wheat grains and their associated soils collected throughout Japan were carried out in order to obtain TFs under equilibrium conditions. We focused on rice and wheat, because the consumption of cereals is very high in Japan and other Asian countries. About 40-50 elements such as Cs, Sr, Th and U in plant and soil samples were measured by ICP-MS and ICP-OES. From the data, TFs of stable elements were calculated; among the values, TFs of Cs and Sr for rice and wheat were compared with the TFs of 137Cs and 90Sr. Using the elements' concentrations data, we proposed a `Reference rice' (brown rice and polished rice) and a `Reference paddy soil' to provide elemental composition data which can serve as reference values in mathematical transfer models and which allows the comparison of data for other crops.