An assessment of the natural radiation dose to wildlife in England and Wales was made to determine the contribution it may make to the total radiation dose estimated during environmental impact assessments. Significant use was made of systematic datasets for environmental media (stream sediments, stream waters and soils), in particular those produced by the Geochemical Baseline Survey of the Environment (G-BASE) project. This provided extensive, although variable, coverage for different elements and sample types after normalisation of data to account for changes in sampling and analysis over time. Almost complete coverage for K in stream sediments was achieved by merging G-BASE and Wolfson Atlas data. This required normalisation of the Wolfson data to the G-BASE results. Coverage was improved greatly for U and Th in sediments, and K, U and Th in soils, by using the strong relationship between soils and sediments and geology (both solid and superficial) to extrapolate the data. The total U, Th and K data were used to derive activity concentrations of 238U and 232Th series radionuclides and 40K. External dose rates to wildlife were then estimated from derived media concentrations; internal dose rates were estimated from measured activities in biota or activities predicted using recommended concentration ratios.

Transfer factors of 226Ra, 210Pb and 210Po from soilcontaminated with naturally occurring radioactive materials (NORM) in oilfields to somegrazing plants were determined using pot experiments. Contaminated soil was collected froma dry surface evaporation pit from a Syrian oilfield in the Der Ezzor area. Five types ofplants (Atriplex halimus L., Atriplex canescens, Atriplex Leucoclada Bioss,Alfalfa and Bermuda grass) were grown and harvested three times over two years.The results show that the mean transfer factors of 226Ra from the contaminatedsoil to the studied plant species were 1.6 × 10-3 for Atriplexhalimus L., 2.1 × 10-3 for Atriplexcanescens, 2.5 × 10-3 for Atriplex LeucocladaBioss, 8.2 × 10-3 for Bermuda grass, and thehighest value was 1.7 × 10-2 for Alfalfa. Transferfactors of 210Pb and 210Po were higher than 226Ra TFs byone order of magnitude and reached 7 × 10-3, 1.1 × 10-2,1.2 × 10-2, 3.2 × 10-2 and 2.5 × 10-2for Atriplex halimus, Atriplex canescens, Atriplex Leucoclada Bioss, Bermuda grassand Alfalfa, respectively. The results can be considered as basevalues for transfer factors of 226Ra, 210Pb and 210Po insemiarid regions.

In this paper we use the FASSET framework to estimate absorbed dose rates for biota within the Chernobyl exclusion zone. The estimated doses are compared to observed biological effects within the Chernobyl exclusion zone and effects expected from summaries of existing knowledge and the extent of contamination. Although paucity of observations under conditions of chronic irradiation makes direct comparison difficult, the biological effects observed in the Chernobyl exclusion zone over the period considered here (1988-2003) are broadly in agreement with those which may have been expected.

La portion bleue (400–500 nm) du rayonnement visible stimule spécifiquement certains cônes et bâtonnets de la rétine. L’énergie véhiculée par ces longueurs d’onde est transférée par absorption aux pigments spécifiques. Cette énergie est suffisante pour produire des radicaux libres et de l’oxygène singulet. Des sources intenses riches en rayonnement bleu peuvent induire au niveau de la rétine des lésions soit limitées et passagères phototoxiques, soit pour de plus fortes énergies, des lésions thermiques plus ou moins définitives. Les lésions phototoxiques, par leur répétition pourraient faire le lit de la dégénérescence maculaire liée à l’âge (DMLA). Dès lors, il convient d’attirer l’attention sur les risques potentiellement liés aux éclairages modernes tels que lampes dites « lumière du jour », les lampes compactes fluorescentes économisant l’énergie (CFLs) et les diodes émettrices de lumière (LEDs) pour lesquelles une vigilance spécifique s’impose.

The biological responses induced by low-dose chronic gamma exposure of hydroponically grown Arabidopsis thaliana, irradiated during a full life cycle (seed to seed) were investigated. Applied dose rates were 2300, 375 and 85 µGray h-1. Plants (roots and shoots) were harvested after 24 day (inflorescence emergence), at 34 days (∼50% of flowers open) and at 54 days (silice ripening). Gamma exposure significantly reduced root weight compared to the control but no clear effect of dose rate level on root dry weight was observed. Leaf weight was significantly reduced at the highest irradiation level, only after 54 days exposure. ED-10 was estimated at 10 µGy h-1. Seed germination was not affected by gamma irradiation. For several of the stress enzymes studied enzyme capacity was generally stimulated at the low and intermediate gamma irradiation level compared to the control and highest irradiation level. No pattern was observed in concentration or reduction state of the non-enzymatic antioxidants, ascorbate and glutathione. Lipid peroxidation products in leaves were present highest at full flowering and decreased with exposure level at this growth stage. At the other two growth stages, lipid peroxidation products were unaffected by gamma treatment.

Born in the fifties together with the emergence of the nuclear technologies, radioecology is a scientific discipline that primarily addresses environmental issues relevant to radioprotection. With a current membership of nearly 600 worldwide, the International Union of Radioecology was founded in the seventies as a non-governmental knowing society dedicated to the development and the promotion of this discipline. The scientific directions taken in Radioecology have been drastically influenced in the past by the Chernobyl accident, which forced a focus on environmental transfers through the environment to feed human radioprotection needs. Currently, a profound evolution is underway towards more ecological effects research and studies, under the driving pressure of the raise of society’s concern on environmental issues and the concomitant re-boost of nuclear industry to face global warming and the future energetic demands. The IUR plays a central role within this evolution which is described here in more details along a description of its four major tools of action: dedicated task groups; workshops, seminars and conferences; training courses; web site tool for information and communication. Finally, together with the recent election of a new Board of Council to manage the Union, the main lines of the new strategic plan for the coming years are given.

Within the framework of the Water Management Master plan, a bioindicator network (RINBIO) was deployed all along the French Mediterranean coast (1,800 km), using man-made cages containing mussels (Mytilus galloprovincialis) to assess contamination by heavy metals, persistent organic products and radionuclides. The caging technique compensated for the scarcity of natural shellfish stocks in significant parts of the coast and enable comparison between sites regardless of their physicochemical and trophic characteristics. Among the 103 stations of the entire program, 40 were selected for the measurement of anthropogenic radionuclides by high-efficiency gamma-spectrometry. Biometrics parameters of the each mussel samples, including `condition index' as an indicator of soft part growth, is correlated with radionuclides activities, to help correct raw data from differences in bioaccumulation between the various sites in relation to their trophic levels. A comprehensive picture of the distribution of radionuclides at such a large spatial scale is provided and the contribution of the Rhone River input, so far the main source for the coastal zone, is investigated.

The levels of gross alpha and beta natural radioactivities in surface, underground and drinking waters consumed by the urban and rural population living in Lagoa Real Uranium Province of central south Bahia state, Brazil were determined in several samples collected from urban public supply of drinking water and, in the rural area, from dug and drilled wells and also from small dams and reservoirs supplied with rainfall. After pre-concentration, the samples were evaporated under an infrared lamp on an inox planchet and subsequently counted on a thin end-window low-background proportional counter, namely Berthold LB 770. Preliminary results show natural radiation levels varying from 0.02 ± 0.001 Bq/L to 0.80 ± 0.04 Bq/L for gross alpha activity and from 0.010 ± 0.006 to 3.0 ± 0.2 Bq/L for gross beta activity. Some values exceed the 2004 WHO recommendation levels that the screening levels for drinking water below which no further action is required are 0,5 Bq/litre for gross alpha activity and 1 Bq/litre for gross beta activity. However, as we are dealing with natural radiation in a well-known high background radiation area, more studies are needed.

Assessment tools and frameworks have been developed that allow environmental assessments to be conducted and which can be used to demonstrate whether non-human species are protected from the impact of exposure to ionising radiation released under regulation. Frameworks are often tiered, increasing in the level of complexity, input data requirements and need for expert involvement as the assessment moves to successively higher tiers. These are, conceptually, similar to assessment approaches available for chemical risk assessment. What criteria (e.g. numeric benchmarks) should be used, and how these should be defined, are currently under debate, but it is likely that use will be made of approaches developed for setting assessment criteria for chemicals. However it will be necessary to ensure that any assessment criteria developed are fit for use in a regulatory context. This paper reviews the similarities and differences between regulation of, and assessment methods for, chemicals and radioactive substances and presents recommendations regarding how components of chemicals risk assessment may be adopted for radioactive substances.

Implantée à Ganagobie, la société Isotopchim était spécialisée dans la synthèse de molécules organiques radioactives (carbone-14). En 2001, l'OPRI est intervenu à la demande de la Préfecture afin d'évaluer l'impact dosimétrique et par conséquent le risque sanitaire lié à la contamination du site et son extension géographique. L'étude de la répartition spatiale du carbone-14 a mis en évidence des niveaux de radioactivité très importants dans différentes parties de l'usine et notamment le laboratoire avec une contamination surfacique supérieure à 20 000 Bq/cm2. Cette étude a également révélé l'association de matières fortement radioactives avec des produits chimiques très inflammables stockés dans des conditions critiques. Suite aux recommandations de l'OPRI, un périmètre de sécurité a été mis en place autour de l'usine afin d'éviter toute dispersion incontrôlée de la radioactivité. La cartographie de l'activité massique du 14C a mis en évidence un marquage spécifique décroissant en fonction de la distance par rapport au point de rejet d'effluents gazeux et de la dispersion atmosphérique liée aux conditions climatiques locales. Dans un rayon de 50 mètres autour de l'usine, le marquage radioactif est important dans les sols (66 000 Bq/kg C) et les végétaux (25 000 Bq/kg C). Néanmoins, malgré des scénarii extrêmes, les calculs de dose ont révélé des valeurs très inférieures à la limite réglementaire fixée par la directive Euratom 96/29 (1 mSv/an). Ce site représente un cas assez rare de contamination manifeste par le 14C. Il peut donc conduire a posteriori à une étude in situ des processus de répartition, d'élimination ou de concentration du carbone-14 dans les sols et les indicateurs biologiques.

In a survey on uranium and 226Ra concentrations in water distributed by Finnish waterworks, 548 samples were analysed that covered drinking water networks servicing 84% of all consumers. Among all consumers, the mean and median uranium concentrations at the point of use were 0.58 and 0.15 μg L–1. The mean uranium concentration in drinking water produced from groundwater was 0.88 μg L–1, and when surface water was used in production the mean concentration was only 0.15 μg L–1. 226Ra concentrations were generally below our detection limit of 0.01 Bq L–1. The annual effective doses to the public arising from these radionuclides were only a few microsieverts, and the 0.1 mSv limit laid down in the EU Drinking Water Directive was not exceeded in any of the studied water distribution networks.

L’utilisation du tritium dans les réacteurs CANDU (Canada Deutérium Uranium), dansl’industrie, pour la production de sources et de peintures luminescentes, dansl’exploration pétrolière et gazière, dans les hôpitaux pour des tests diagnostiques, enradiothérapie et en recherche, rend le contrôle de ses rejets particulièrement importantau Canada. Ces rejets sont réglementés et étroitement surveillés par la Commissioncanadienne de sûreté nucléaire (CCSN). Certains groupes d’intérêt et de citoyensprétendent cependant que l’incertitude scientifique sur les effets du tritium sur la santéet l’environnement est telle que la réglementation des installations rejetant ou utilisantdu tritium serait inadéquate. Pour répondre à ces inquiétudes, la CCSN a demandé à sonpersonnel d’entreprendre le projet intitulé « Études sur le tritium ».Dans le cadre de ce projet, le devenir du tritium dans l’environnement ainsi que seseffets sanitaires, ont été étudiés au moyen de mesures directes sur le terrain ainsi qu’àtravers la revue de la littérature scientifique la plus récente sur le sujet. Ce projet apermis de conclure que les mesures de radioprotection concernant le tritium ainsi que lesmécanismes utilisés pour le réglementer sont adéquats pour protéger la santé et lasécurité des Canadiens.

L'étude de la distribution spatiale et de l'évolution temporelle des isotopes du plutonium (238Pu, $^{239{-}240}$Pu) chez des espèces indicatrices (Fucus serratus, Patella sp., Mytilus edulis) a été réalisée le long des côtes de la Manche. Plusieurs époques ont été considérées, 1982-1983, 1990-1993 et 1996. Les concentrations des différents isotopes sont inférieures à 1 Bq kg-1 sec pour les années les plus récentes. Une diminution de ces concentrations depuis plusieurs années est observée et elle est associée à la diminution desquantités de plutonium rejetées par l'usine de la Hague. Des gradients de distribution des isotopes le long des côtes apparaissent pour les fucus. La différence entre les rapports isotopiques des espèces et des rejets conduit à discuter des diverses sources de radioactivité influençant les niveaux de plutonium. Enfin, les facteurs de concentration sont définis.

The accident at the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) in March 2011 led toan unprecedented direct input of artificial radioactivity into the marine environment. TheInstitute for Radioprotection and Nuclear Safety was requested by the French authoritiesto investigate the radioecological impact of this input, in particular the potentialcontamination of products of marine origin used for human consumption. This articledescribes the close link between the responses provided and the availability of the data,as well as their nature and ability to meet the requirements of expert investigation.These responses were needed: (i) to evaluate the inputs of radionuclides into the marineenvironment, (ii) to understand their dispersion in seawater, and (iii) to estimate theirtransfer to the biota and sediments. Three phases can be distinguished which characterisethese processes during the accident and post-accident periods. The first phase correspondsto an emergency phase during which no measurements were available on samples from themarine environment. It involved the formulation of hypotheses based solely on theexpertise of the Institute for Radioprotection and Nuclear Safety. The second phasestarted when the Japanese authorities provided measurements of the concentrations ofradionuclides in seawater. Although these data were not yet adapted to addressing theproblems of radioecology, the scenarios could then be refined and the estimates developedin more detail. During the third phase, the accumulation of data over the course of timemade it possible to study the phenomena in an appropriate way. The chronology of theevents shows that it is essential to have (i) significant measurements of concentrationfrom samples collected in the various matrices of the marine environment, regularlyupdated and sufficiently well-documented, (ii) samples of seawater collected at theearliest opportunity as close as possible to the damaged site to characterise the sourceterm, and (iii) a numerical tool allowing rapid modelling of the dispersion ofradionuclides in seawater, as well as their transfer to sediments and the biota,ultimately for the purpose of estimating the dose to humans.

Activities of radionuclides were measured in five species of fish (grayling, dace, crucian carp, pike, cod) sampled in the Yenisei River (Siberia, Russia) in the vicinity of the Mining-and-Chemical Combine (ROSATOM) from 2007 to 2010, with a gamma-spectrometer (Canberra, USA). The analyses of samples of organs and tissues of fish species revealed artificial (46Sc, 51Cr, 54Mn, 58,60Co, 59Fe, 65Zn, 85Sr, 99Mo, 103,106Ru, 137Cs, 141,144Ce) and natural (7Be, 40K) radionuclides in fish organs and tissues, including edible ones. The major percent (up to 80%) of 137Cs and 40K activity occurred in muscles of fish species, which also contained considerable percentages of 60Co (up to 70%) and 65Zn (up to 20%). Seasonal changes in the intake of artificial radionuclides by zoobenthos-feeding fish species (grayling and dace) were recorded and they were followed by an activity concentration increase in internal organs. The dramatic increase in radionuclide intake by grayling coincided with the change of diet source. Hence, the feeding behavior of fish can change the fluxes of artificial radionuclides in the Yenisei River. The most effective diet transfer of a radionuclide from gammarus to grayling (muscles and total body) was recorded for 40K (1.3) and much less effective for artificial nuclides.

METAS réalise l’étalon primaire de la dose absorbée dans l’eau pour les faisceaux d’électrons de haute énergie entre 5 MeV et 22 MeV avec un dosimètre chimique basé sur une solution de Fricke. Cette réalisation comprend deux étapes. Tout d’abord, une expérience d’absorption totale d’un faisceau monoénergétique étroit d’énergie et de charge connues permet de déterminer la réponse de la solution de Fricke à la dose absorbée. Ensuite, l’irradiation de sachets de solution dans des faisceaux de qualités thérapeutiques assure le raccordement métrologique des étalons secondaires. Certaines corrections appliquées aux valeurs mesurées sont obtenues à l’aide de simulations Monte Carlo. Les pertes dues principalement à l’émission de Bremsstrahlung lors de l’expérience d’absorption totale dépendent de l’énergie des électrons et de la taille du récipient de solution de Fricke, et sont comprises entre 2,7 % et 8,2 % de l’énergie du faisceau incident. Les facteurs de transfert pour obtenir la dose absorbée dans l’eau à partir des mesures des sachets varient faiblement avec l’énergie entre 0,58 % et 0,80 %.

Bien que le tritium soit un radionucléide existant à l’état naturel, sa présence dans l’environnement est souvent associée à la production d’électricité d’origine nucléaire. À l’occasion de la construction du nouveau réacteur EPR à Flamanville et de renouvellement d’autorisations de rejets pour des sites existants, cette publication a pour objectif de résumer la connaissance scientifique, les mesures réalisées autour des sites et les études d’impact dans l'environnement et chez l'homme pour ces deux radionucléides.

This work aims at determining early effects of uranium on the green microalga Chlamydomonas reinhardtii. First, the global effect on growth rate inhibition of exponentially-growing cultures was assessed on favourable conditions for uranium bioavailability (e.g. pH=5), EC50-24hrs equals roughly to 150 nM whatever the uranium isotopic composition considered (depleted U or 233U). Then, the sensitivity of different parameters representative of (i) oxidative stress (GSH/[GSH + 0.5 GSSG] ratio) (ii) metal detoxifying (phytochelatins production) and (iii) photosynthetic activity (chlorophyll fluorescence) was tested. Setting assay of different forms of glutathione and phytochelatins by HPLC was firstly optimised with cadmium-contaminated cells. This assay completed by chlorophyll fluorescence and algal growth was subsequently applied on samples contaminated by 150 nM of depleted uranium or 233U. No phytochelatin was produced in our experimental conditions. No difference of GSH/[GSH + 0.5 GSSG] ratio was shown between control and contaminated algae. This result suggests that the algae could be stressed before contamination due to culture condition. Chlorophyll fluorescence measurement showed photosynthetic activity inhibition after 24 hrs, in the same way for depleted uranium and 233U. Thus, the effect observed on the photosynthetic activity could be mainly attributed to the chemical toxicity of the metal.

La dosimétrie individuelle des neutrons constitue une des difficultés actuelles de la radioprotection des travailleurs. La dosimétrie dite active (opérationnelle) est réglementaire depuis mars 1999 ; les valeurs des seuils recommandées par la CIPR 60 applicables en mai 2000 rendent nécessaire la mise en place d'une nouvelle génération de dosimètresneutrons. L'Institut de protection et de sûreté nucléaire (IPSN) a mené, au cours de ces dernières années, l'étude d'un dosimètre électronique individuel pour les neutrons satisfaisant aux spécifications d'un cahier des charges défini par le groupe de travail " dosimétrie neutrons " réunissant les principaux acteurs du cycle nucléaire français. Courant1998, l'IPSN a engagé un transfert de technologie vers la société Saphymo ; celle-ci commercialisera fin 2000 le premier dosimètre individuel électronique pour les neutrons, le Saphydose-n, répondant à la norme CEI 1323. Ce dosimètre,d'un encombrement réduit, permettra d'évaluer l'équivalent de dose individuel Hp(10) dans des champs mixtes neutron-gamma. Il pourra être utilisé dans toutes les installations du cycle électronucléaire, sans connaissance préalable de l'énergie moyenne du spectre des neutrons et du rapport neutron-gamma. Le dosimètre Saphydose-n pourra être raccordé aux bornes existantes des dosimètres gamma pour la lecture des informations et pour la charge des accumulateurs.

Health Canada maintains detector networks across Canada. One of these networks consists of NaI(Tl) detectors that measure air KERMA [1]. Located beside the NaI(Tl) detector in Ottawa is a radioxenon analyzer [2] that measures the activity concentration of 131m, 133m, 133, 135Xe directly. The ICRU-accepted KERMA to activity concentration conversion factor for 133Xe, for a semi-infinite cloud measured 1 m off the ground, is 9.68 pGy/hr per Bq/m3 [3]. However, on various dates, the two detectors in Ottawa reported a conversion value of 2.6 ± 0.2 pGy/hr per Bq/m3; we have resolved this discrepancy [4] and have expanded on the study of other isotopes by focusing on the NaI(Tl) detector. Greater accuracy in the conversion value between the air KERMA and activity concentration will assist meteorological modellers in verifying their models [1]. Two Monte Carlo methods were used in this investigation. The first is the analogue geometry where the detector is immersed in a semi-infinite radioactive source. A second method is to apply a reciprocal transform of the analogue geometry. This expedited the calculation of larger clouds. By using these two methods together, we have calculated new values for KERMA rate to activity concentration for 4 of isotopes of noble gases, namely 131mXe, 133mXe, 85Kr, 85mKr, 135Xe.