Uncertainty analysis in internal dose calculations for cerium considering the uncertainties of biokinetic parameters and S values.

Radioactive cerium and other lanthanides can be transported through the aquatic system into foodstuffs and then be incorporated by humans. Information on the uncertainty of reported dose coefficients for exposed members of the public is then needed for risk analysis. In this study, uncertainties of dose coefficients due to the ingestion of the radionuclides 141Ce and 144Ce were estimated. According to the schema of internal dose calculation, a general statistical method based on the propagation of uncertainty was developed. The method takes into account the uncertainties contributed by the biokinetic models and by the so-called S values. These S-values were derived by using Monte Carlo radiation transport simulations with five adult non-reference voxel computational phantoms that have been developed at Helmholtz Zentrum München, Germany. Random and Latin hypercube sampling techniques were applied to sample parameters of biokinetic models and S values. The uncertainty factors, expressed as the square root of the 97.5th and 2.5th percentile ratios, for organ equivalent dose coefficients of 141Ce were found to be in the range of 1.2-5.1 and for 144Ce in the range of 1.2-7.4. The uncertainty factor of the detriment-weighted dose coefficient for 141Ce is 2.5 and for 144Ce 3.9. It is concluded that a general statistical method for calculating the uncertainty of dose coefficients was developed and applied to the lanthanide cerium. The dose uncertainties obtained provide improved dose coefficients for radiation risk analysis of humans. Furthermore, these uncertainties can be used to identify those parameters most important in internal dose calculations by applying sensitivity analyses.

Distribution and bioavailability of ceria nanoparticles in an aquatic ecosystem model.

Along with the increasing utilization of engineered nanoparticles, there is a growing concern for the potential environmental and health effects of exposure to these newly designed materials. Understanding the behavior of nanoparticles in the environment is a basic need. The present study aims to investigate the distribution and fate of ceria nanoparticles in an aquatic system model which consists of sediments, water, hornworts, fish and snails, using a radiotracer technique. Concentrations of ceria in the samples at regular time intervals were measured. Ceria nanoparticles were readily removed from the water column and partitioned between different organisms. Both snail and fish have fast absorption and clearance abilities. Hornwort has the highest bioaccumulation factors. At the end of the experiment, sediments accumulated most of the nanoparticles with a recovery of 75.7 ± 27.3% of total ceria nanoparticles, suggesting that sediments are major sinks of ceria nanoparticles.

Cyclotron production of radioactive CeO(2) nanoparticles and their application for in vitro uptake studies.

Nowadays, a wide variety of nanoparticles (NPs) are applied in different fields such as medical science and industry. Due to their large commercial volume, the OECD Working Party on Manufactured Nanomaterials (NMs) has proposed to study a set of 14 nanomaterials, one of which being cerium oxide (CeO(2)). In particular, CeO(2) based NPs are widely used in automotive industry, healthcare, and cosmetics. In this paper, we propose a method for the production of radioactive CeO(2) NPs.We demonstrate that they maintain the same physicochemical characteristics as the "cold" ones in terms of size distribution and Zeta potential; we develop a new protocol to assess their cellular interaction in immortalized mouse fibroblast cell line Balb/3T3, a model for the study of basal cytotoxicity and carcinogenic potential induced by chemicals and in the present case by NPs. Experimental result of this work, which shows a quasi-linear concentration-uptake response of cells, can be useful as a reference dose-uptake curve for explaining effects following biological uptake after exposure to CeO(2) NPs.

The placental transfer of cerium: experimental studies and estimates of doses to the human fetus from 141Ce and 144Ce.

PURPOSE: To measure the transfer of cerium from mother to fetus in experimental animals and estimate doses to the human fetus following intakes of radioisotopes of Ce. MATERIALS AND METHODS: Cerium-141 in chloride solution was administered intravenously to rats at different stages of pregnancy (days 9.5, 12.5 or 18.5), and retention in the embryo/fetus and associated tissues was measured 3 days later in each case. Retention in rat fetal tissues on day 21.5 (shortly before birth) was also measured after administration of 141Ce chloride 1 month prior to conception or 141Ce citrate on day 18.5. Cerium-141 chloride was administered to guinea pigs on day 50 for measurements of fetal retention on day 57 (shortly before birth). RESULTS: Retention of 141Ce in the rat embryo/fetus, measured at 3 days after administration to the mother, increased from about 0.00002% of injected activity per embryo/fetus on day 12.5 to about 0.014% on day 21.5 of gestation. However, the relative concentrations of 141Ce in the embryo/fetus and mother (CF:CM ratio) were between 0.005 and 0.01 in each case. After 141Ce administration prior to conception, retention by the rat fetus on day 21.5 was substantially lower than after short-term administration. Comparison of retention of 141Ce on day 21.5 after administration on day 18.5 as either chloride or citrate showed similar levels in maternal tissues but greater transfer to the fetus (CF:CM ratio of 0.03). Retention in the guinea pig fetus in late gestation at 7 days after administration of (141)Ce chloride was about 0.05% injected activity per fetus, corresponding to a CF:CM ratio of about 0.02. CONCLUSION: These results and other published animal data have been used to specify CF:CM ratios for use in the calculation of doses to the human fetus. The values used were 0.05 for intakes during pregnancy and 0.01 for intakes prior to conception. Doses to the offspring after maternal ingestion of 141Ce or 144Ce are largely due to irradiation from activity in the maternal colon and are insensitive to CF:CM. After inhalation, however, absorption of Ce to blood is much greater and doses to the offspring are dominated by the contribution from activity in the fetus, and therefore dependent on the CF:CM ratio used.

The toxicity of insoluble cerium-144 inhaled by beagle dogs: non-neoplastic effects.

The biological effects of inhaled beta-particle-emitting radionuclides are not well known. The non-neoplastic diseases induced by an inhaled, relatively insoluble form of cerium-144 ((144)Ce) were studied in beagle dogs exposed to graded activity levels of (144)Ce in fused aluminosilicate particles by a single, brief inhalation exposure and observed for their life span. The initial lung burdens (ILBs) achieved ranged from 0.000093-7.6 MBq (144)Ce/kg body weight. The (144)Ce was retained in the lung with an effective half-life of about 190 days. Significant (144)Ce was translocated to the tracheobronchial lymph nodes, and the concentration exceeded that of the lung at about 400 days after inhalation exposure. Significant radiation doses were delivered to the lung and tracheobronchial lymph nodes and to the heart adjacent to the tracheobronchial lymph nodes. Radiation pneumonitis was the predominant non-neoplastic disease. The dose response for radiation pneumonitis indicated that an ILB of 1.4 MBq/kg would cause death from radiation pneumonitis in 50% of the exposed dogs. This ILB resulted in a pulmonary dose to death of about 350 Gy. The tracheobronchial lymph nodes developed lesions in dogs with ILBs lower than those causing radiation pneumonitis. The overall results of this study, however, showed that (144)Ce, inhaled in an insoluble form, did not cause any unique or inexplicable biological effects in dogs or cause effects at unusually low doses that might call current radiation protection guidelines into question.

Biological effects of inhaled 144CeCl3 in beagle dogs.

The biological effects of 144Ce were studied in beagle dogs that were exposed to graded activity levels of 144CeCl3 via a single, brief inhalation exposure and observed for their life span. The long-term retained body burdens ranged from 0.06 to 13 MBq/kg with a median of 1.2 MBq/kg. After a short residence time in the lung, most of the 144Ce was translocated to liver and skeleton, where the 144Ce was retained with a half-time approaching the physical half-life of 144Ce, 284 days. Significant radiation doses were delivered to the lung, 28 Gy (median) and 2.5-370 Gy (range); liver, 68 Gy (median) and 6.1-250 Gy (range); and skeleton, 21 Gy (median) and 1.9-100 Gy (range). Lesions induced by the beta-particle radiation were noted in the lung, liver, skeleton, bone marrow, and oral and nasal mucosae closely associated with bone. Early deaths (within 2.5 years) were generally related to hematological dyscrasia, radiation pneumonitis, or hepatocellular degeneration and atrophy. Neoplasms that occurred relatively early, from 2.2-6.8 years after exposure, were noted in the liver, bone, bone marrow and oral mucosa closely associated with bone. Neoplasms that occurred later, beyond 7 years after exposure, were noted in the liver, lung and nasal mucosa closely associated with bone. Increased numbers of neoplasms were not found in two other organs that had relatively high radiation doses, namely the thyroid and kidney. Only one primary bone tumor was noted, but 11 tumors of bone-associated tissues (oral and nasal mucosae and bone marrow) were found. Radiation doses and effects in tissues adjacent to bone, especially those of epithelial or marrow origin, should be considered when determining risks from internally deposited bone-seeking radionuclides, such as 144Ce. The property of 144Ce in depositing on and remaining associated with bone surfaces for long times may be an important factor in the radiation dose to bone marrow and epithelium adjacent to bone.

Regional and arterial localization of radioactive microparticles after local delivery by unsupported or supported porous balloon catheters.

Catheter-mediated intramural delivery of pharmaceutical agents after angioplasty is a potential method to reduce postangioplasty restenosis. The efficacy of such delivery has been limited both by an incomplete initial intramural deposition of delivered agents and by rapid diffusion of soluble agents from the site of delivery. The local delivery of microparticulate agents results in prolonged retention of material at the delivery site. Accordingly this study was designed to evaluate the complementary issue of the initial delivery efficiency and pattern of localization of microparticles after local catheter-mediated delivery with two types of porous balloons. These two types were a "standard" porous balloon (PB) in which hydraulic pressure both inflated the balloon and infused the agents and a porous balloon with a mechanical undergirding that permitted mechanical expansion (PB/ME) before agent infusion. Radioactive cerium 141-labeled microparticles (11.4 microns diameter) were locally delivered into atherosclerotic rabbit femoral arteries after angioplasty to test the hypothesis that use of the PB/ME apparatus would yield enhanced intramural particle deposition and decreased systemic administration by increased balloon-wall contact before microparticle infusion. Six animals underwent infusion with the PB catheter, and seven animals underwent infusion with the PB/ME catheter. An image of the in vivo particle distribution was obtained with a gamma camera during infusion, immediately after infusion, and 1, 3, and 7 days after infusion. Tissue samples from the artery, periadventitia, thigh, calf, and foot musculature, and liver were obtained at animal death, and retained radioactivity was measured with a well counter.(ABSTRACT TRUNCATED AT 250 WORDS)

LB-145 a new radioactive isotope eliminating product with high selectivity.

LB-145 is a macrocyclic ligand, which forms, 200 times more stable complex with Stroncium (Sr) ions, than with calcium ones. The product is not toxic, it has no effect on circulation, respiratory system. 85,90Sr and 144Ce were given oral, i.p., s.c. or by inhalation, LB-145 either prophylactic or 30 (60) minutes after the radiointoxication i.v. or i.p. to the animals. The isotope contents of the organism were measured by whole body autoradiography, liquid scintillation, or by NK 350 ratemeter. One injection given prophylactic inhibited the incorporation of isotopes into the organism, within 24 hours after radiointoxication 75-80% of the isotopes were excreted by urine and faeces on the first day, 90-95% excreted on the first week. Also the isotope contents of femur and scissors were mobilised. The suggested human dose-0.5 g/70 kg bw-can be life-saving antihavaric injection.

Repeated inhalation exposure of rats to aerosols of 144CeO2. I. Lung, liver, and skeletal dosimetry.

To develop a better understanding of the influence of cumulative radiation dose and dose rate to the lungs on the biological responses to inhaled radionuclides, several studies are in progress at this institute in which laboratory animals have been exposed once or repeatedly to aerosols of insoluble particles containing 144Ce or 239Pu. In the study reported here, F344 rats were exposed repeatedly to aerosols of 144CeO2 beginning at 94 days of age to reestablish desired lung burdens of 1.9, 9.2, 46, or 230 kBq of 144Ce every 60 days for 1 year (seven exposures). Other 94-day-old rats were exposed once to achieve similar desired initial lung burdens of 144Ce. Older rats were exposed once to achieve desired initial lung burdens of 46 or 230 kBq when 500 days of age, the age of the repeatedly exposed rats when exposed for the last time. Control rats were either unexposed, sham-exposed once or repeatedly, or exposed once or repeatedly to stable CeO2. Approximately equal numbers of male and female rats were used. The cumulative beta-radiation doses to the lungs, liver, and skeleton of rats exposed repeatedly were similar to those of rats with similar total lung burdens of 144Ce from a single inhalation exposure. The average beta-radiation dose rate to the lungs of the rats exposed repeatedly was about one-fifth of that in rats with similar total lung burdens after a single exposure.

Behavior of neutron-activated uranium dioxide dust particles in the gastrointestinal tract of the rat.

The behavior of neutron-irradiated, simulated Chernobyl UO2 particles containing 141Ce, 144Ce, 95Zr, 95Nb, and 103Ru in the gastrointestinal tract was investigated to obtain basic information for dosimetric and risk analyses of nuclear accidents. After the UO2 particles were administered to rats intragastrically, the distribution and retention of specific radionuclides were studied by using whole-body autoradiography and gamma-spectrometric analysis of tissues. None of the radionuclides were detected in liver, kidney, muscle, bone, brain, blood, and urine. Approximately 98% of the total administered radioactivity was excreted in feces within 3 days. A two times greater intestinal retention (about 6%) of 95Nb than for the other radionuclides was observed 1 day after administration. The results indicate that this kind of relatively insoluble particulate material is not absorbed or retained significantly in the epithelial cells of the intestinal wall. Fallout particles containing high-energy beta sources, 106Ru and 144Ce, result in a very high radiation dose (up to several Gy/day) in the vicinity of a hot particle. Niobium-95 with low average beta energy (0.043 MeV (100%)) does not increase the total dose to the GI tract significantly despite its longer retention in the intestine. Evaluation of the biological effects of these particles in the GI tract by using a dosimetric model based on uniform distribution of activity may be misleading.

Revascularisation of bone grafts in rats.

Revascularisation of syngeneic and allogeneic intramuscular bone grafts have been studied using radioactive microspheres to measure the ingrowth of blood vessels. New bone formation and resorption were measured by 85strontium uptake and by graft weight reduction. Revascularisation, and mineralisation rate were significantly higher in syngeneic grafts than in allogeneic grafts at two, three and six weeks after implantation. The syngeneic grafts lost weight faster indicating that the allogeneic grafts resorbed more slowly. The ingrowth of new vessels is impaired in allogeneic bone, and this probably inhibits the rate of bone formation and resorption of the grafts.

An optimization strategy for a biokinetic model of inhaled radionuclides.

Models for material disposition and dosimetry involve predictions of the biokinetics of the material among compartments representing organs and tissues in the body. Because of a lack of human data for most toxicants, many of the basic data are derived by modeling the results obtained from studies using laboratory animals. Such a biomathematical model is usually developed by adjusting the model parameters to make the model predictions match the measured retention and excretion data visually. The fitting process can be very time-consuming for a complicated model, and visual model selections may be subjective and easily biased by the scale or the data used. Due to the development of computerized optimization methods, manual fitting could benefit from an automated process. However, for a complicated model, an automated process without an optimization strategy will not be efficient, and may not produce fruitful results. In this paper, procedures for, and implementation of, an optimization strategy for a complicated mathematical model is demonstrated by optimizing a biokinetic model for 144Ce in fused aluminosilicate particles inhaled by beagle dogs. The optimized results using SimuSolv were compared to manual fitting results obtained previously using the model simulation software GASP. Also, statistical criteria provided by SimuSolv, such as likelihood function values, were used to help or verify visual model selections.

[Morphometric research in determining the absorbed dose in the lungs formed from aspirated radionuclides]. / Morfometricheskie issledovaniia pri opredelenii pogloshchennoi dozy v legkikh, obrazuemoi aspirirovannymi radionuklidami.

Macro- and microtopography of the distribution of aspirated colloidal 144CeF3 in autographs of rabbit lung total sections were examined with the help of a monitoring-measuring device "Videoplan" and microcomputer. Quantitative assessment of photoemulsion-blackening areas at the site of radionuclide concentration has confirmed that aspirated radionuclides are distributed in the lungs according to the same laws as nonradioactive aerosols: the relation of total microvolumes of actually irradiated pulmonary tissue to the entire lung volume long after radionuclide entry is shown; a possibility to use these data for determination of an actually absorbed dose in microvolumes of pulmonary tissue during aspiration of radionuclides is considered.