A greenhouse experiment was set up to evaluate the potential of enhanced phytoextraction to clean up U and heavy metal contaminated soils. One soil had a naturally high U concentration; the other soil was impacted by the radium extraction industry. Enhancement of solubility and uptake by plants (ryegrass and Indian mustard) was monitored after addition of 5 chemical amendments: citric acid, ammonium citrate-citric acid mixture, oxalic acid, EDDS and NTA. Solubilisation and uptake were highly influenced by the amendment applied and soil-plant combinations. For U, citric acid, the ammonium citrate-citric acid mixture or EDDS were most effective in increasing U uptake. EDDS was most effective in increasing Cu in mustard and ryegrass and Pb in ryegrass shoots. For other metals, increase in uptake was limited to at most a factor 5. Percentages annually removed with biomass ranged from 0.0002% to 1.52%., and were lowest for U, Cr and Pb and highest for Cd. A targeted 10% reduction in soil contaminant would require 7 years for Cd, 35 and 52 years for Cu and Zn, 203 and 384 years for U and Pb and 9433 years for Cr. Phytoextraction is hence not a feasible technique to decontaminate historically contaminated soils.

The study investigates accumulation of radionuclides in 5 species of berry shrubs in forests of the Yenisei River basin (the Krasnoyarskii Krai, Russia). Activity concentrations of 60Co, 90Sr, 137Cs, 238U and transuranic elements in aboveground organs of the shrubs have been determined and their transfer factors calculated. Analysis of the calculated TFs shows that shrubs concentrate 90Sr more effectively than other study elements (TF = 0.25–1.9). The highest concentration of 137Cs is recorded in the berries and leaves of Ribes nigrumand Rubus idaeus. For these species, the range of 137Cs TFs (0.006–0.027) overlaps with the range of 238U TFs (0.004-0.018). For the aboveground parts of Ribes nigrum, TFs for transuranic radionuclides (0.01–0.056) are similar to or higher than the TFs for 238U and 137Cs.

The 5-year multi-national project EURANOS, funded by the European Commission, started in April 2004. Integrating 17 national emergency management organisations with 33 research institutes, it brings together best practice, knowledge and technology to enhance the preparedness for Europe's response to any radiation emergency and long term contamination. After four years of operation the following achievements can be stated. Two handbooks to assist national and local authorities in the management of contaminated food production systems and inhabited areas in Europe have been developed in conjunction with a wide range of European stakeholders. A governance framework for the sustainable rehabilitation of long term contaminated territories has been developed and tested in France. Its implementation in Norway has started. A consistent methodology for calculating the best estimate possible of current radiological situation in both contaminated agricultural and contaminated inhabited areas has been developed. The migration of RODOS (Real-time On-line Decision Support System) to the operating system LINUX is completed. A mass consistent wind field model was implemented together with a particle model for complex terrain. A complete re-engineering of the system has started aiming to incorporate all the user's recommendations collected within the demonstration projects and the operational use of the system in emergency management organisations.

La directive européenne 2006/25/CE, relative à l’exposition des travailleurs auxrayonnements optiques, prévoit l’évaluation des risques au poste de travail par la mesureet/ou le calcul. L’objectif de cette étude était de permettre à des organismes de contrôlede mettre en œuvre la directive en mettant à leur disposition une méthodologie simpled’évaluation des risques in situ, compatible avec leurs moyens. Cette étude a doncconsisté à faire un état du marché, acquérir quelques appareils de mesure de coûtraisonnable (radiomètres et spectroradiomètres) et ensuite évaluer leurs performances. Lesrésultats des mesures effectuées sur 5 lampes de spectres divers, à l’aide de cesappareils, ont été comparés à ceux donnés par un spectroradiomètre de laboratoire priscomme référence. De cette étude il est ressorti qu’aucun d’eux ne permet de mesurer avecune précision acceptable le rayonnement émis par des sources de différentes natures surl’ensemble du domaine spectral compris entre 180 et 3 000 nm. Les radiomètres ne sont pasadaptés à la mesure de sources émettant sur un domaine spectral étroit. Lesspectroradiomètres à simple monochromateur ou à barrettes CCD linéaires présentent quant àeux des erreurs importantes attribuables à la lumière parasite (stray light). Cependant,l’approche d’une méthode de correction de cette lumière parasite a montré qu’il étaitpossible d’améliorer la précision de ces appareils.

En 2000, des flux de rayonnement anormalement élevés ont été détectés sur certaines plages du littoral camarguais. Les sables du littoral camarguais ont alors fait l’objet d’une caractérisation radiologique montrant des activités moyennes de quelques dizaines de Bq kg-1 en uranium-238 et thorium-232 d’une part, et l’existence de points chauds à plus de 1000 Bq kg-1 d’autre part ; voire plus sur deux plages : l’une située à l’Est du phare de Beauduc, l’autre située à l’Est du phare de l’Espiguette. Cette radioactivité, d’origine naturelle, est responsable de l’exposition des personnes fréquentant ces deux dernières plages relativement isolées, mais néanmoins accessibles à tout public. L’Institut de radioprotection et de sûreté nucléaire a réalisé une évaluation des doses susceptibles d’être reçues par des personnes fréquentant ces deux dernières plages, en se basant sur des mesures et des prélèvements effectués in situ, en établissant expérimentalement la solubilité des sables dans les fluides gastrique et intestinal, et en formulant des hypothèses sur la fréquentation des lieux (scénarios). La dose annuelle maximale ainsi évaluée est de l’ordre de 0,8 mSv pour des adultes et 0,5 mSv pour les enfants ; valeurs vraisemblablement très prudentes dans lesquelles la dose par exposition externe prédomine largement.

Les études épidémiologiques concernant des personnes exposées aux rayonnementsionisants restent à la base des estimations de risque de cancer radioinduitchez l'homme. La principale étude ayant servi à l'élaboration des normesde radioprotection est celle des survivants d'Hiroshima et Nagasaki. Lesmalades traités par radiothérapie ou ayant subi des radiographies dans un butdiagnostique, ainsi que des groupes de travailleurs exposés professionnellementfournissent également nombre d'informations sur le risque de radiocarcinogenèse.Ces études épidémiologiques permettent d'affirmer avec certitude l'existenced'un risque pour certains cancers après irradiation à fortes doses, souvent délivréesà fort débit de dose. Par contre, aucune conclusion n'est possible pour lesfaibles doses et faibles débits de dose. On est donc obligé d'extrapoler auxfaibles doses et faibles débits les risques connus pour les fortes doses enutilisant divers modèles mathématiques pour la relation entre la dose et l'effetobservé. Une autre difficulté vient de la grande période de latence des cancersradio-induits, ce qui explique que tous les cancers en excès n'aient pas encoreété observés dans les populations irradiées étudiées. Là encore, on a recours àdes modèles mathématiques pour projeter sur la vie entière le risque de cancersexcédentaires. Les estimations de risque de radiocancers sont, par conséquent,entachées de nombreuses incertitudes, puisqu'elles varient en fonction dumodèle utilisé. D'autres incertitudes proviennent des données de base, en particulierde la dosimetrie, et se majorent lorsqu'il s'agit de transposer les risquesd'une population à une autre.L'UNSCEAR, en 1988, a proposé de nouvelles estimations pour le risque dedécès excédentaires par cancers sur la vie entière qui serait compris entre 4 et11 % par gray ; ces valeurs représentent une réévaluation des précédentesestimations d'un facteur 1,6 à 4,4, et sont en grande partie la conséquence del'utilisation de modèles de projection différents. D'autre part, elles s'appuientuniquement sur les observations des survivants d'Hiroshima et Nagasaki, alorsque les études de malades fournissent un risque moindre. Enfin, l'UNSCEAR nedéfinit pas précisément le facteur de réduction utilisable pour passer des fortesdoses et forts débits de dose aux faibles doses et faibles débits qui restecompris entre 2 et 10. En raison des nombreuses incertitudes persistantes, il nesemble pas justifié de modifier actuellement les normes de radioprotection.

There is much current interest in managing and manipulating radionuclide transfer from soils to plants, either for `safe' crops or for phytoextraction of radionuclide contaminated soils. Potentially there is biodiversity in plant uptake that might aid these efforts. We have established the effects of phylogeny (evolutionary history) on the uptake of numerous heavy metal and nutrient elements. Here, using the same Residual Maximum Likelihood techniques, we report phylogenetic effects on radionuclide uptake by plants derived from databases of several hundred species of plants we have collated over recent years. There are differences of at least two orders of magnitude in the concentration to which plants take up isotopes of Cs, Sr, Cl, Ru, S, and I. When analysed using hierarchical Analysis of Variance coded using a recent molecular phylogeny of flowering plants it is clear that for no radionuclide is all the variation inter-specific. Rather, for all radionuclides some of the inter-taxa variation is associated with higher taxonomic levels. In general, therefore, groups of plants with high and low uptake of radionuclides, and that might be useful for managing or manipulating radionuclide uptake, can be delineated. Here we discuss some of these groups and how they might be useful.

The Incident and Emergency Centre (IEC) of the International Atomic Emergency Agency(IAEA) is the global focal point for preparedness and response to nuclear and radiologicalincidents and emergencies irrespective of their cause. In the area of preparedness theCentre continuously works to develop standards and guidance for strengthening MemberStates’ preparedness; practical tools and training programs to assist Member States inpromptly applying the standards and guidance; and organizes a variety of training eventsand exercises. This paper provides an overview of the information presented in the IAEASafety Standards and Guidance in the area of emergency preparedness and response.

Les variations passées du carbone-14 atmosphérique peuvent être reconstruites sur les derniers 50 000 ans par l'étude des différences entre âges carbone-14 et âges calendaires. Liées en premier lieu à la modulation géomagnétique du taux de production du 14C par le rayonnement cosmique et aux variations d'origine climatique du stock de 14C océanique, ces variations ont atteint un facteur 2 au début du paléolithique supérieur. Des variations de même amplitude ont été provoquées par les essais nucléaires militaires des années 50 et 60. La contribution cumulée de l'industrie nucléaire depuis ses débuts jusqu'à nos jours est de l'ordre d'un centième des quantités relâchées dans l'environnement par les retombées des explosions nucléaires atmosphériques. Représentant annuellement 14 % du taux de production naturel de 14C, cette contribution au rapport isotopique 14C/12C est actuellement contrebalancée par l'effet de dilution du 14C par les émissions de CO2 fossile (effet Suess).

Des zones anatomiques superficielles exposées au rayonnement gamma d'une source d'iridium 192 ont été suivies in vivo par imagerie de résonance magnétique. Une étude de cas a été effectuée sur trois miniporcs irradiés à des doses de 96, 32 et 64 Gy à la peau, sur la région dorsale entre les vertèbres T7 et L4. Les acquisitions réalisées sur un système à 1,5 tesla montrent que les images pondérées en temps de relaxation spin-spin (T2) font apparaître une diminution du signal pendant les deux premières semaines suivant l'irradiation. Les variations observées, analogues dans la peau, le tissu adipeux et le muscle sous-cutané, sont plus fortes dans la peau. Cette observation indique que l'imagerie de résonance magnétique, qui peut être un moyen de diagnostic précoce des brûlures radiologiques en profondeur, peut également renseigner de façon spécifique et précoce sur le comportement du tissu cutané.

The comparison of strength of bystander effect induction in human lymphocytes by rho0 (complete loss of mitochondrial DNA) and rho+ (with fully functional mtDNA) strains of Saccharomyces cerevisiaewas carried out. The cultures of human peripheral blood were experimentally contaminated with nonirradiated or X-ray irradiated yeast cells (haploid rho0 and rho+ strains of S. cerevisiae). The doses of irradiation were 1 and 10 Gy. Well spread human metaphases were scored for chromosomal aberrations (CA). It was found that nonirradiated yeast cells (no matter rho0 or rho+) had no effect on lymphocytes chromosomal stability. Statistically significant increased level of CA was observed in lymphocytes incubated with irradiated rho+ yeast cells. The increasing of the CA was dose independent. However, after cocultivation with irradiated rho0 cells the bystander effect was revealed for dose 10 Gy only and his manifestation was mild in comparison with rho+ data. Thus, our findings suggest that strength of bystander effect depends on existence of mitochondrial DNA and normally functioning mitochondria.

In the present paper, we estimated backscattering factors for the TLD and active personaldosimeters using 662 keV gamma-ray photons on a PMMA surface, which are, for the TLD,1.12; Dosicard, 1.116; DRD, 0.99; and Saphydose, 1.073, and on a water slab phantomsurface; for the TLD, 1.115; Dosicard, 1.112; DRD, 1; and Saphydose, 1.059. Thebackscattering factor contribution for the Saphydose is nearly half that of the TLD andDosicard, whereas it is zero for the DRD. The DRD underestimates Hp(10)by 10.3–11.6%, whereas for the Saphydose it is 3.4–5% compared with the TLD or Dosicard.The response of the DRD to Hp(10) is nearly independent of the phantom,whereas the TLD, Dosicard and Saphydose require phantoms for calibration for personalmonitoring. It is observed that the PMMA phantom contributes slightly higherbackscattering compared with the water slab phantom. The backscattering factor of theselected dosimeters is comparable with ICRU tissue already reported.

Seasonal indoor radon concentration was surveyed, and the annual effective dose was estimated for the residents in some dwellings near the registered uranium mining lot areas, considered as one of the potential radon-prone area. The range of indoor radon concentration in each dwelling was from 17.7 to 1,610 Bq⋅m−3. The range of annual effective dose due to inhaled radon of the resident in each dwelling was from 0.93 to 20.5 mSv.

The new technologies were developed for spent nuclear fuel (SNF) condition operative monitoring and search for the lost objects with SNF at the sea bottom using Kr-85. The new paradigm of sea radioecology based on extensive research was proposed. The investigations include a preliminary experimental study of kinetics of fission products (Kr-85 and Cs-137) release from SNF, a subsequent expedition to the Arctic, as well as modeling radionuclides transfer in a near-bottom layer by means of fractal formalism using hydrological data on the expedition area [1,2]. Series of original experimental studies on Kr-85 and Cs-137 release from SNF during corrosion in sea water were conducted in 2002–2010. Time dependence of fission products (FP) release was measured in laboratory under conditions typical of a near-bottom water layer in the Novaya Zemlya Basin. Another important result was received during the expedition to the Arctic in the fall of 2000. The H-3 anomaly was recognized in the surface layer of the Kara Sea in the Novaya Zemlya Basin (228 ± 9.1 TU vs.10–15 TU in the Arctic on average!). This anomaly is located 100 miles south from the dumped reactor of atomic icebreaker “Lenin”. So it can be caused by SNF from the reactors of icebreaker “Lenin” or nuclear submarine K-140.

Lead-210 is a natural radioactive isotope and a decay product of the Uranium-238 decay chain found in the natural environment along with Radon-222 and Polonium-210. Lead-210 contribution to the internal exposure of man through ingestion is 20% but represents 70% of the internal exposure of man through inhalation due to the uranium and thorium decay series.

Transfer of lead-210 in the environment has been relatively poorly studied when compared to other radionuclides (Caesium-137, Strontium-90, Cobalt-60, Tritium, Carbon-14, etc.) even if we register a recent increase in the number of scientific publications. Therefore, this study reviews experimental data concerning the transfers of Lead-210 in the different compartments (atmosphere, freshwaters, sediments, soils, plants, animals) of continental environments (terrestrial and freshwater) from its natural sources.

Moreover, it compares these data with those concerning the stable isotopes of lead. Indeed, stable lead is found in all the terrestrial and freshwater ecosystems but with an important variation in its concentration according to location and sampling type. Such a global contamination of the environment is mainly due to its industrial use. Lead toxicity is coming from its physiological behaviour similar to those of essential elements such as calcium and magnesium. A list of transfer factors for Lead-210 and stable isotopes of lead between the different compartments of the terrestrial and freshwater ecosystems is provided.

The main conclusion of this review is that the behaviours of Lead-210 and stable isotopes of lead are quite similar in terrestrial environments although some discrepancies are noted in freshwater environments. The nature of these discrepancies is discussed.

Tritium concentrations of groundwater samples from the Environmental Monitoring Program at IPEN (Institute of Nuclear and Energetic Researches), São Paulo, Brazil, covering the years 2000 to 2003, were determined by liquid scintillation counting and the results laid in the range of 20 Bq$\cdot$L-1 to 91 Bq$\cdot$L-1. The effective committed dose for general public considering the highest concentration value is 1.3 μSv$\cdot$y-1, which is below the ICRP dose limit of 1mSv$\cdot$y-1. Tritium concentration of radioactive liquid effluents samples from the IEA-R1 research reactor storage tank showed values from 3.6×103 Bq$\cdot$L-1 to 6.2×103 Bq$\cdot$L-1, approximately 1000 times below the Brazilian daily discharge limit of 3.7×106 Bq$\cdot$L-1.

In Northern Europe the use of tree biomass for production of energy is mostly based on thinning of forests, harvest residues, stumps from final cutting, bark of commercial roundwood, and organic waste of pulp industry. Results based on field experiments allow estimations of 137Cs activity removed from forests in wood fuel, and also the activity returned in ash used as a fertiliser. After one fertilisation treatment in three types of coniferous forests the activity concentration of 137Cs in wood fuel and ash was reduced to a fraction of 0.3 to 08 of activities in products from unfertilised forests. The improved tree growth and lowering activity concentrations of 137Cs in trees and understorey after fertilisation refer to reduction of human radiation exposure in Chernobyl-affected areas in the long term. Thereby radiation doses to workers handling the ash and members of the public using forests will gradually decrease faster than through radioactive decay only. A documented and traceable ash recycling history of forests is important for all users of forests.

One of the most serious problems occurring during coal extraction in Upper Silesia in Poland is caused by waters with high salinity which also often contain high concentrations of natural radionuclides, mainly 226Ra and 228Ra. Similar phenomenon is also observed in oil and gas industry. On the Norwegian continental shelf, substantial amounts of produced waters containing elevated levels of 226Ra and 228Ra are discharged to the sea. All of these facts outlined elsewhere in the reports serious resulted in contamination of wide areas surrounding mines and other related industries. Research studies conducted so far have provided a lot of data concerning the scale of this phenomenon. But nowadays, all of them should be reconsidered in the light of newest recommendation of the state of-the-art radiation protection. Namely, such waste deposited directly into the environment creates significant risk to the non-human biota that currently must be assessed as well. On the other hand, such scenario of exposure to ionising radiation creates a good opportunity to observe potential effects of low and protracted doses to the living organisms occurring on contaminated areas, especially plants.

Decision makers must react in a prompt and appropriate manner in various emergency situations. The bases for decisions are often predictions produced with decision support systems (DSS). Actual radiation measurement data can be used to improve the reliability of the predictions. Data assimilation is an important link between model calculations and measurements and thus decreases the overall uncertainty of the DSS predictions. However, different aspects have to be taken into account for the optimal use of the data assimilation technique: different countries may have differing measurement strategies and systems as well as differing calculation models. The scenario and the amount and composition of radionuclides released may vary. In this paper we analyse the situation during and after an accident and draw up a list of recommendations that can help modellers to take into account the measurements that are best suited for data assimilation.