Absorption of plutonium compounds in the respiratory tract.

In order to optimise the monitoring of potentially exposed workers, it is desirable to determine specific values of absorption for the compounds handled. This study derives specific values of absorption rates for different chemical forms of plutonium from in vitro and animal (monkeys, dogs, mice, rats) experiments, and from human contamination cases. Different published experimental data have been reinterpreted here to derive values for the absorption parameters, f(r), s(r) and s(s), used in the human respiratory tract model currently adopted by the International Commission on Radiological Protection (ICRP). The consequences of the use of these values were investigated by calculating related committed effective doses per unit intake. Average and median estimates were calculated for f(r), s(r), and s(s) for each plutonium compound, that can be used as default values for specific chemical forms instead of the current reference types. Nevertheless, it was shown that the use of the current ICRP reference absorption types provides reasonable approximations. Moreover, this work provides estimates of the variability in pulmonary absorption and, therefore, facilitates analyses of the uncertainties associated with assessments, either from bioassay measurements or from prospective calculations, of intake and dose.

Updating the ICRP human respiratory tract model.

The ICRP Task Group on Internal Dosimetry is developing new Occupational Intakes of Radionuclides (OIR) documents. Application of the Human Respiratory Tract Model (HRTM) requires a review of the lung-to-blood absorption characteristics of inhaled compounds of importance in radiological protection. Where appropriate, material-specific absorption parameter values will be given, and for other compounds, assignments to default Types will be made on current information. Publication of the OIR provides an opportunity for updating the HRTM in the light of experience and new information. The main possibilities under consideration relate to the two main clearance pathways. Recent studies provide important new data on rates of particle transport from the nasal passages, bronchial tree (slow phase) and alveolar region. The review of absorption rates provides a database of parameter values from which consideration can be given to deriving typical values for default Types F, M and S materials, and element-specific rapid dissolution rates.

Development of a database: DACTARI for a radiotoxic element ranking methodology.

Dosimetric impact studies aim at evaluating potential radiological effects of chronic or acute releases from nuclear facilities. A methodology for ranking radionuclides (RN) in terms of their health-related impact on the human population was first developed at CEA with specific criteria for each RN that could be applied to a variety of situations. It is based, in particular, on applying physico-chemical criteria to the complete RN inventory (present in the release or in the source term) and on applying norms related to radiation protection and chemical toxicology. The initial step consisted in identifying and collecting data necessary to apply the methodology, with reference to a previous database of long-lived radionuclides (LLRN, with half-lives ranging from 30 to 10(14) y) containing 95 radionuclides. The initial results have allowed us to identify missing data and revealed the need to complete the study for both toxic and radiotoxic aspects. This led us to the next step, developing a specific database, DAtabase for Chemical Toxicity and Radiotoxicity Assessment of RadIonuclides (DACTARI), to collect data on chemical toxicity and radiotoxicity, including acute or chronic toxicity, the chemical form of the compounds, the contamination route (ingestion, inhalation), lethal doses, target organs, intestinal and maternal-foetal transfer, drinking water guidelines and the mutagenic and carcinogenic properties.

Current and future radionuclide speciation studies in biological media.

Radionuclides may be released into the environment accidentally or incidentally, which could raise health risks when ingested or inhaled by humans. In order to study the behaviour of radionuclides in the human organism (metabolism, retention, excretion), knowledge of radionuclide speciation is indispensable: speciation governs the transfer, bioavailability and toxicity of elements and is also of considerable interest for decorporation. In this context, the Commissariat à l'Energie Atomique has created a working group on speciation to share data both on thermodynamic constants and on speciation analysis methods of interest to chemists, environmentalists and biologists. The initial focus was on the 31 radionuclides described in different International Commission on Radiological Protection models (HRTM, HAT) and the National Council on Radiation Protection model (wound). Particular attention was devoted to selecting the inorganic and organic ligands, most representative of biological media. The base applied to speciation in solution and at interfaces and solubility (BASSIST) thermodynamic database was developed for this purpose. The aim of this paper is to present the state of the art on radionuclide speciation tools within biological media and to emphasise some missing data in order to orient future research.

MEDOR, a didactic tool to support interpretation of bioassay data after internal contamination by actinides.

A didactic software, MEthodes DOsimètriques de REférence (MEDOR), is being developed to provide help in the interpretation of biological data. Its main purpose is to evaluate the pertinence of the application of different models. This paper describes its first version that is focused on inhalation exposure to actinide aerosols. With this tool, sensitivity analysis on different parameters of the ICRP models can be easily done for aerosol deposition, in terms of activity and particle number, actinide biokinetics and doses. The user can analyse different inhalation cases showing either that dose per unit intake cannot be applied if the aerosol contains a low number of particles or that an inhibition of the late pulmonary clearance by particle transport can occur which contributes to a 3-4 fold increase in effective dose as compared with application of default parameters. This underlines the need to estimate systematically the number of deposited particles, as well as to do chest monitoring as long as possible.

Comparison of Prussian blue and apple-pectin efficacy on 137Cs decorporation in rats.

Cesium-137 (137Cs) is one of the most important nuclear fission elements that contaminated the environment after the explosion of the Chernobyl nuclear power plant in Ukraine (1986). The aim of the study was to compare the efficacy of two chelating agent, Prussian blue and apple-pectin on 137cesium decorporation in rats. Rats were intravenously injected with a solution of 137cesium (5 kBq per rat). Chelating agents, Prussian blue or apple-pectin were given immediately after Cs contamination and during 11 days by addition of each chelating agent in drinking water at a concentration corresponding to 400 mg kg(-1) day(-1). Efficiency was evaluated 11 days after contamination (at the end of treatment) through their ability to promote Cs excretion and to reduce the radionuclide accumulation in some retention compartments (blood, liver, kidneys, spleen, skeleton and in the remaining carcass). In these conditions after treatment with Prussian blue a fivefold increase in fecal excretion of Cs was observed and was associated with a reduction in the radionuclide retention in the main organs measured. In contrast, no significant differences were observed between untreated rats and rats treated with apple-pectin. These observations were discussed in terms of ability of pectins to bind Cs and compared to recently published results obtained after treatment of Cs-contaminated children with this chelate.

Metal(loid)s and radionuclides cytotoxicity in Saccharomyces cerevisiae. Role of YCF1, glutathione and effect of buthionine sulfoximine.

The presence of heavy metal(loid)s in soils and waters is an important issue with regards to human health. Taking into account speciation problems, in the first part of this report, we investigated under identical growth conditions, yeast tolerance to a set of 15 cytotoxic metal(loid)s and radionuclides. The yeast cadmium factor 1 (YCF1) is an ATP-Binding Cassette transporter mediating the glutathione detoxification of heavy metals. In the second part, metal(loid)s that could be handled by YCF1 and a possible re-localisation of the transporter after heavy metal exposure were evaluated. YCF1 and a C-terminal GFP fusion, YCF1-GFP, were overexpressed in wild-type and Deltaycf1 strains. Both forms were functional, conferring a tolerance to Cd, Sb, As, Pb, Hg but not to Ni, Zn, Cu, Ag, Se, Te, Cr, Sr, Tc, U. Confocal experiments demonstrated that during exposure to cytotoxic metals, the localisation of YCF1-GFP was restricted to the yeast vacuolar membrane. In the last part, the role of glutathione in this resistance mechanism to metal(loid)s was studied. In the presence of heavy metals, application of buthionine sulfoximine (BSO), a well-known inhibitor of gamma-glutamylcysteine synthetase, led to a decrease in the cytosolic pool of GSH and to a limitation of yeast growth. Surprisingly, BSO was able to phenocopy the deletion of gamma-glutamylcysteine synthetase after exposure to Cd but not to Sb or As. In the genetic context of gsh1 and gsh2 yeast mutants, the critical role of GSH for Cd, As, Sb and Hg tolerance was compared to that of wild-type and Deltaycf1.

An interdisciplinary approach to investigate the impact of cobalt in a human keratinocyte cell line.

Since in nuclear power plants, risks of skin contact contamination by radiocobalt are significant, we focused on the impact of cobalt on a human cutaneous cell line, i.e. HaCaT keratinocytes. The present paper reports an interdisciplinary approach aimed at clarifying the biochemical mechanisms of metabolism and toxicity of cobalt in HaCaT cells. Firstly, a brief overview of the used instrumental techniques is reported. The following parts present description and discussion of results concerning: (i) toxicological studies concerning cobalt impact towards HaCaT cells (ii) structural and speciation fundamental studies of cobalt-bioligand systems, through X-ray absorption spectroscopy (XAS), ab initio and thermodynamic modelling (iii) preliminary results regarding intracellular cobalt speciation in HaCaT cells using size exclusion chromatography/inductively coupled plasma-atomic emission spectroscopy (SEC/ICP-AES) and direct in situ analysis by ion beam micropobe analytical techniques.

ICRP Publication 134: Occupational Intakes of Radionuclides: Part 2.

Abstract ­: The 2007 Recommendations of the International Commission on Radiological Protection (ICRP, 2007) introduced changes that affect the calculation of effective dose, and implied a revision of the dose coefficients for internal exposure, published previously in the Publication 30 series (ICRP, 1979, 1980, 1981, 1988b) and Publication 68 (ICRP, 1994b). In addition, new data are available that support an update of the radionuclide-specific information given in Publications 54 and 78 (ICRP, 1988a, 1997b) for the design of monitoring programmes and retrospective assessment of occupational internal doses. Provision of new biokinetic models, dose coefficients, monitoring methods, and bioassay data was performed by Committee 2, Task Group 21 on Internal Dosimetry, and Task Group 4 on Dose Calculations. A new series, the Occupational Intakes of Radionuclides (OIR) series, will replace the Publication 30 series and Publications 54, 68, and 78. Part 1 of the OIR series has been issued (ICRP, 2015), and describes the assessment of internal occupational exposure to radionuclides, biokinetic and dosimetric models, methods of individual and workplace monitoring, and general aspects of retrospective dose assessment. The following publications in the OIR series (Parts 2­5) will provide data on individual elements and their radioisotopes, including information on chemical forms encountered in the workplace; a list of principal radioisotopes and their physical half-lives and decay modes; the parameter values of the reference biokinetic model; and data on monitoring techniques for the radioisotopes encountered most commonly in workplaces. Reviews of data on inhalation, ingestion, and systemic biokinetics are also provided for most of the elements. Dosimetric data provided in the printed publications of the OIR series include tables of committed effective dose per intake (Sv per Bq intake) for inhalation and ingestion, tables of committed effective dose per content (Sv per Bq measurement) for inhalation, and graphs of retention and excretion data per Bq intake for inhalation. These data are provided for all absorption types and for the most common isotope(s) of each element. The electronic annex that accompanies the OIR series of reports contains a comprehensive set of committed effective and equivalent dose coefficients, committed effective dose per content functions, and reference bioassay functions. Data are provided for inhalation, ingestion, and direct input to blood. The present publication provides the above data for the following elements: hydrogen (H), carbon (C), phosphorus (P), sulphur (S), calcium (Ca), iron (Fe), cobalt (Co), zinc (Zn), strontium (Sr), yttrium (Y), zirconium (Zr), niobium (Nb), molybdenum (Mo), and technetium (Tc).

In vitro chemical and cellular tests applied to uranium trioxide with different hydration states.

A simple and rapid in vitro chemical solubility test applicable to industrial uranium trioxide (UO3) was developed together with two in vitro cellular tests using rat alveolar macrophages maintained either in gas phase or in alginate beads at 37 degrees C. Industrial UO3 was characterized by particle size, X-ray, and IR spectra, and chemical transformation (e.g., aging and hydration of the dust) was also studied. Solvents used for the in vitro chemical solubility study included carbonates, citrates, phosphates, water, Eagle's basal medium, and Gamble's solution (simulated lung fluid), alone, with oxygen, or with superoxide ions. Results, expressed in terms of the half-time of dissolution, according to International Commission on Radiological Protection (ICRP) classification (D,W,Y), varied for different hydration states of UO3, showing a lower solubility of hydrated UO3 in solvents compared to basic UO3 or UO3 heated at 450 degrees C. Two in vitro cellular tests on cultured rat alveolar macrophages (cells maintained in gas phase and cells immobilized in alginate beads) were used on the same UO3 samples and generally showed a lower solution transfer rate in the presence of macrophages than in the culture medium alone. The results of in vitro chemical and cellular tests were compared, with four main conclusions: a good reproducibility of the three tests in Eagle's basal medium the effect of hydration state on solubility, the classification of UO3 in terms of ICRP solubility criteria, and the ability of macrophages to decrease uranium solubility in medium.

Role of alveolar macrophage lysosomes in metal detoxification.

The intracellular behaviour of different toxic mineral elements inhaled as soluble aerosols or as insoluble particles was studied in the rat by electron microscopy, electron probe microanalysis, and electron microdiffraction. This study showed that, after inhalation, aerosols of soluble elements like cerous chloride, chromic chloride, uranyl nitrate, and aluminium chloride, are concentrated in the lysosomes of alveolar macrophages and are precipitated in the lysosomes in the form of insoluble phosphate, probably due to the activity of acid phosphatase (intralysosomial enzyme). Also, after inhalation of crystalline particles that are insoluble or poorly soluble in water such as the illites (phyllosilicates), ceric oxides (opaline), and industrial uranium oxides (U3O8), the small crystals are captured by the alveolar macrophage lysosomes and transformed over time into an amorphous form. This structural transformation is associated with changes in the chemical nature of particles inhaled in the oxide form. Microanalysis of amorphous deposits observed after inhalation of uranium or ceric oxides has shown that they contain high concentrations of phosphorus associated with the initial elements cerium and uranium. These different processes tend to limit the diffusion of these toxic elements within the organism, whether they are inhaled in soluble form or not.

Comparative absorption parameters of Pu and Am from PuO2 and mixed oxide aerosols measured after in vitro dissolution test and inhalation in rats.

PURPOSE: To compare specific absorption parameter values obtained from in vitro dissolution studies (this paper) and in vivo experiments (data published by Ramounet et al, 2000) and to determine their influence on Dose Per Unit Intake (DPUI) calculations. MATERIALS AND METHODS: Experiments were performed on plutonium oxide (PuO2) and two Mixed Oxide (MOx) preparations containing 5% Pu (w/w) made according to the industrial process in vitro using a static test and in vivo after rat inhalation. RESULTS: Behaviour of Pu and Am shows, in vitro, at shorter times, a greater rapid dissolution fraction f(r) for Pu (factor 10) and Am (factor 2) with MOx powders compared with PuO2, whereas in vivo results show a greater fraction f(r) for Pu (factor 5) and Am (factor 15) with PuO2 compared with MOx powders. This phenomenon has not been observed for slow dissolution absorption parameter s(s). The in vivo parameters for Pu and Am in these materials were very close to the default values recommended by International Commission for Radiological Protection for default Type S. CONCLUSIONS: Results obtained have shown that solubility of Pu from the mixed oxide was higher than that of Pu from PuO2. Nevertheless, no significant difference was observed between the three compounds in the corresponding dose coefficients in vivo or in vitro. Therefore, for these particular compounds, variation in the chemical composition of the aerosols had no significant influence on DPUI. Consequently, in vitro, the dissolution test can provide a good estimate of the in vivo behaviour. Studies of variation of % Pu (w/w) from MOx are in progress in our laboratory to confirm these conclusions.

In vitro solubility of uranium tetrafluoride with oxidizing medium compared with in vivo solubility in rats.

A simple in vitro solubility test for uranium tetrafluoride (UF4) was developed to investigate the effects of addition of enzymes, proteins or gases such as O2 to synthetic biological fluid or Gamble solvent. The tests were conducted concomitantly with an in vivo inhalation experiment using male rats. In the presence of Gamble solvent alone, UF4 exhibited class Y behaviour with a dissolution half-time of 300-500 days. However, when oxygen or carbonates were added to the Gamble solvent, UF4 displayed class W behaviour, with a half-time of 25-50 days. Lastly, in the presence of oxygen and pyrogallol, which simulates the action of the enzyme NADPH, the superoxide ion (O2-) was formed, which appears to have a dominant role in the oxidation of U4+ to U6+. Under these conditions UF4 behaved like a class D compound, and had a dissolution half-time of only 2-3 days. These latter results correlated with those of the inhalation experiment in which the dissolution half-time was calculated to be between 2.5 and 5.2 days. The data are also in agreement with urine monitoring data obtained for workers exposed to UF4 over a 20-year period.

Efficacy of 3,4,3-LIHOPO for reducing the retention of uranium in rat after acute administration.

Decorporation therapy is the only known effective method of reducing the radiation dose to persons following accidental internal contamination with transportable radionuclides. Deposits of actinides in bone should be minimized because development of osteosarcoma appears to be related to internal exposure. In contrast with other actinides, such as plutonium or americium where chelating agent treatment is efficient, the therapeuric approaches used for cases of uranium contamination are widely ineffective. This is the first report on in vivo efficacy of a chelating agent, a siderophore analogue code named 3,4,3-LIHOPO, after systematic exposure to natural uranium in the rat. Using the classical antidotal therapy (sodium bicarbonate) for comparison, this ligand has been investigated for its ability to remove uranium from rats after intravenous or intramuscular injection as nitrate. Following an immediate single intramuscular or intravenous injection of 3,4,3-LIHOPO (30 mumol.kg-1) urinary excretion of uranium was greatly enhanced with a corresponding reduction 24 h later in kidney and bone uranium content (to about 20 and 50% of the control rat respectively). Under identical experimental conditions, sodium bicarbonate (640 mumol.kg-1) reduced the uranium content in kidney in kidney and bone only to about 90 and 70% of controls respectively, and there was less enhancement of uranium excretion. However, when treatment was delayed by 30 min and administered intraperitoneally, there was no marked difference in retention and excretion of uranium between the two compounds. As this ligand showed no apparent irreversible toxicity at effective dosages, it is concluded that the administration of the 3,4,3-LIHOPO chelating agent represents potentially a most significant advance for prompt treatment of uranium contamination, while a more detailed investigation is necessary on the possible advantage when treatment delayed.

The effects of the initial lung deposit on uranium biokinetics after administration as UF4 and UO4.

This study was designed to assess the effect of the initial lung deposit (ILD) on uranium biokinetics in rats after intracheal instillation of biologically soluble uranium compounds. Rats received various doses of either UO4 or UF4 dust. The uranium content was determined in the kidneys, lungs, remaining carcass, urine and faeces at intervals of up to 30 days. The percentages of uranium absorbed into blood, transferred to tissues, and excreted in urine were independent of the uranium lung deposit for the two compounds. The K/K + U ratio 24 h after installation (K is the per cent of uranium retained in the kidneys and U the per cent excreted in urine) which can be used to evaluate kidney function, was essentially constant in the range from 0.02 to 12.5 microg U g(-1) kidneys.

Efficacy of ethane-1-hydroxy-1,1-bisphosphonate (EHBP) for the decorporation of uranium after intramuscular contamination in rats.

PURPOSE: To obtain compounds that will effectively reduce the fixation of uranium in its main target organs: bone and kidney. There is an urgent need for a chelating agent that is suitable and available for human use. MATERIALS AND METHODS: The efficacy of ethane-1-hydroxy-1,1-bisphosphonate (EHBP), already in use as a therapeutic agent, was investigated in animal experiments. The effect of different treatment regimens was investigated on rats (EHBP: 50-100 micromol kg(-1); ligand/uranium ratio 2500 to 5000). RESULTS: The present study shows that one prompt injection of EHBP reduced uranium deposition in kidneys by a factor of five after acute intramuscular contamination in rats. At the same time, the total body uranium in the treated animals was 70% of controls. When the treatment was delayed 30 min after contamination, the kidney content was still reduced by a factor of two. CONCLUSIONS: EHBP has the advantage of clinical acceptance as a therapeutic agent for other purposes and its toxicity has been well studied. It therefore has a role in the treatment of human contamination with uranium.

Efficacy of 3,4,3-LIHOPO for reducing neptunium retention in the rat after simulated wound contamination.

PURPOSE: The ligand 3,4,3-Li(1,2-HOPO) was tested for Np removal after intramuscular injection of 237Np nitrate in rats. MATERIALS AND METHODS: Two experiments were performed, one with simultaneous injection of neptunium and LIHOPO at dosages ranging from 3 to 200 micromol kg(-1) and the other with delayed administration of LIHOPO 30 micromol kg(-1) from 5 min to 30 min after Np injection. RESULTS: The data obtained after simultaneous injections showed that the ligand dosage effectiveness was not linear and depended on the tissues being considered. For bones, the best results were obtained with 200 micromol kg(-1) LIHOPO, where retention was reduced to 11% of controls. Maximum efficacies for removal in liver and kidney were obtained with 30 micromol kg(-1) LIHOPO, where retention was reduced to 39% and 1.6% of controls, respectively. At higher dosages, LIHOPO seemed to have a reverse effect on these tissues, demonstrated by a significant accumulation of the radionuclide. The delayed administration of LIHOPO dramatically decreased its efficacy. When administered 5 min after Np, LIHOPO was still efficient (60%, 37%, 7% of controls in bone, liver, kidneys, respectively) but not when treatment was delayed to 30 min. CONCLUSIONS: These results demonstrated that LIHOPO was able to complex Np at the wound site but not after translocation to blood.

Intracellular behaviour of uranium(VI) on renal epithelial cell in culture (LLC-PK1): influence of uranium speciation.

The main objective of this work was to assess the potentiality of in vitro models to study and understand the uranium-induced cytotoxicity on renal cells. Cytotoxicity and morphological studies were performed in a tubular proximal original established cell line (LLC-PK1 cell line). Dose-dependent cytotoxicity response was obtained with the uranium bicarbonate complex. In vitro experiments revealed a toxicity of uranium-bicarbonate complexes after a 24-h exposition and for concentrations ranging from 7 x 10(-4) M to 10(-3) M. In contrast, a lack of cytotoxicity of uranium(VI) citrate complexes studied using the same experimental conditions was noticed. Furthermore, electron transmission microscopy and X-ray microanalysis studies, after exposition of LLC-PK1 cells to the uranium-bicarbonate system ([U] = 8 x 10(-4) M) revealed that uranium entered into the cells and it was precipitated within the cytoplasmic compartment as uranyl phosphate needles. Similar morphological studies conducted with citrate complexes did not show any intake of uranium by LLC-PK1 cells. Experiments conducted in phosphate free culture medium showed that uranium was incorporated as a soluble material and that the association of the metal with phosphate ions occurred in the cytoplasmic compartment of LLC-PK1 cells.

Uranium-induced Vasoreactivity in Isolated Glomeruli and Cultured Rat Mesangial Cells.

The present study is aimed at investigating direct vasocontractive effects of uranium on two glomerular in vitro models (isolated rat glomeruli and cultured mesangial cells). For this study, sublethal doses of the uranium(VI)-bicarbonate complex were determined by cytotoxicity experiments on confluent cultured mesangial cells. Afterwards, using a morphoquantitative approach (computerized image analyser) the variations of planar surface areas (PSA) of glomeruli and mesangial cells exposed to uranium(VI)-bicarbonate have been assessed. Our results showed a significant reduction of PSA for glomeruli (-9% after 40 minutes of exposure to uranium: [U]=100 mum) and for rat mesangial cells (-14% after 40 minutes), while PSA values for control glomeruli and mesangial cells remain stable (ranging from 2.5 to 3.5% after 40 minutes of exposure to HBSS medium). These findings suggest that uranium renal target is not only the proximal tubule, but demonstrate, for the first time, that non- lethal uranium doses can induce direct vasoactive effects on glomerular structures and especially on mesangial cells.

Influence of uranium(VI) speciation for the evaluation of in vitro uranium cytotoxicity on LLC-PK1 cells.

Very few data are available concerning the in vitro toxicity of uranium. In this work, we have determined the experimental chemical conditions permitting the observation of uranium(VI) cytotoxicity on LLC-PK1 cells. Uranium solutions made either by dissolving uranyl acetate or nitrate crystals, or by complexing uranium with bicarbonate, phosphate or citrate ligands, were prepared and tested. Experiments demonstrated that only uranium solutions containing citrate and bicarbonate ligands concentrations tenfold higher than the metal, were soluble in the cell culture medium. Cytotoxicity studies of all these uranium compounds were performed on LLC-PK1 cells and compared using LDH release, neutral red uptake and MTT assays. Dose dependent cytotoxicity curves were only obtained with uranium-bicarbonate medium. This study has revealed a toxicity of uranium-bicarbonate complexes for 24 h expositions and for concentrations ranging from 7 x 10(-4)-10(-3) M, under these conditions, the CI50 (cytotoxicity index) was evaluated between 8.5 and 9 x 10(-4) M. In contrast, we noticed a lack of cytotoxicity response for uranium(VI)-citrate complexes. Electron transmission microscopy studies revealed, when LLC-PK1 cells were exposed to the uranium-bicarbonate system, that uranium penetrated and precipitated within the cytoplasmic compartment. Morphological studies conducted with citrate complexes did not show any cellular intake of uranium.