Structural genomic damage in plutonium workers

The research objective is assessment of structural genomic damages in plutonium workers. The study group included workers of the Mayak Production Association subject to chronic occupational internal exposure to incorporated ²³⁹Pu and/or external γ-rays. A lymphocyte culture of peripheral blood was chosen as an object of study. The yield of intrachromosomal exchange aberrations of chromosomal type on stained slides was analyzed using fluorescent in situ hybridization, mBAND. Linear relationships were revealed between (a) the total yield of chromosome-type aberrations (intra- and inter-chromosomal ones) and the absorbed dose from external exposure of the red bone marrow (RBM) to γ rays, the absorbed dose from internal exposure of the RBM to α-radiation from incorporated ²³⁹Pu, and ²³⁹Pu body burden, and (b) the yield of intrachromosomal aberrations and an absorbed dose from internal exposure of the RBM to ²³⁹Pu and ²³⁹Pu body burden.     

Mayak worker study: an improved biokinetic model for reconstructing doses from internally deposited plutonium

The plutonium production facility known as the Mayak Production Association was put into operation in June 1948. A high incidence of cancer in the Mayak workers has been related to the level of exposure to plutonium, but uncertainties in tissue doses have hampered development of dose-risk relationships. As part of an effort to improve dose estimates for these workers, the systemic biokinetic model for plutonium currently recommended by the International Commission on Radiological Protection (ICRP) has been modified to reflect recently developed data and facilitate interpretation of case-specific information. This paper describes the proposed model and discusses its implications for dose reconstruction for the Mayak workers.     

Structural genomic damages in workers of plutonium production

The research objective is assessment of structural genomic damages in plutonium workers. The study group included the Mayak nuclear workers subject to chronic occupational exposure to incorporated 239Pu and/or external gamma-rays. The analysis was performed based on the culture of lymphocytes in peripheral blood. The yield of intra-chromosomal exchange aberrations of chromosomal type on stained slides was analyzed using in situ fluorescent hybridization, mBAND. Linear relationships were revealed between (a) the total yield of chromosomal type aberrations (e.g. intra- and inter-chromosomal ones) and an absorbed dose from external exposure of the red bone marrow to gamma-rays, an absorbed dose from internal exposure to a-radiation from incorporated 239Pu; and (b) the yield of intra-chromosomal exchange aberrations of chromosomal type and an absorbed dose from exposure of the red bone marrow to 239Pu and 239Pu body burden.     

Finding sensitive parameters in internal dose calculations for radiopharmaceuticals commonly used in clinical nuclear medicine

Internal dosimetry after incorporation of radionuclides requires standardized biokinetic and dosimetric models. The aim of the present work was to identify the parameters and the components of the models which contribute most to dosimetric uncertainty. For this a method was developed allowing for the calculation of the uncertainties of the absorbed dose coefficients. More specifically, the sampling-based regression method and the variance-based method were used to develop and apply a global method of sensitivity analysis. This method was then used to quantify the impact of various biokinetic and dosimetric parameters on the uncertainty of internal doses associated with the incorporation of seven common radiopharmaceuticals. It turned out that the correlation between biokinetic parameters and time-integrated activity or calculated absorbed dose is strongest when the source and target organ are identical, in accordance with the ICRP and the MIRD approach. According to the ICRP approach, the parameter F_s which describes the fractional distribution of any incorporated radioactivity to organ S, has the greatest correlation with the time-integrated activity in the corresponding source organ or with the calculated dose in the corresponding target organ. In contrast, the MIRD approach suggested several biokinetic parameters with similar correlation. The dosimetric parameters usually contribute more to uncertainty in the calculated dose coefficients than the biokinetic parameters, in both approaches. The results obtained are helpful for the revision of biokinetic models for radiopharmaceuticals, because the most important parameters in clinical applications can now be identified and investigated in future studies.     

Activity estimation and biokinetic analysis of 99mTc-DMSA in renal infant patients using a gamma camera

Biokinetic data from the administration of radiopharmaceuticals is essential in nuclear medicine dosimetry. It has particular significance in children, as their metabolism is very different from adults. Biokinetic models for paediatric patients could therefore need to be adapted to better reflect their absorption, retention and excretion functions, when compared to adults. Obtaining quality in vivo infant or paediatric biokinetic data is then essential to improve the available reference models, which in turn can lead to the optimization of paediatric procedures and protocols in clinical practice.This study analyses the biokinetic behaviour of ^99mTc-dimercaptosuccinic acid (DMSA), in 8 infants aged 4 months to 2 years old, through an imaging study using a gamma camera, and compares the obtained values with those obtained with the reference ICRP biokinetic model. The in vivo data was treated using an adapted methodology from the MIRD 16 pamphlet. Activity curves for the liver, the kidney and the whole body, were built, and new effective absorption, retention and excretion half-lives were estimated, and compared with the reference biokinetic parameters of ICRP 128. The obtained residence time in the kidneys of 2.56 h, has a deviation of 30.8% to the ICRP 128 value of 3.70 h. The obtained maximum uptake in the kidneys was of 0.22/A₀, which compares to the value of 0.31/A₀ for ICRP.The obtained biokinetic parameters were used to estimate the absorbed dose. The obtained dose values are smaller than the reference ICRP 128 ones by 32.1% in the kidneys, and 18.4% in the liver.     

Influence of human biokinetics of strontium on internal ingestion dose of <Superscript>90</Superscript>Sr and absorbed dose of <Superscript>89</Superscript>Sr to organs and metastases

The objective of the present work is to apply the plasma clearance parameters to strontium, previously determined in our laboratory, to improve the biokinetic and dosimetric models of strontium-90 (⁹⁰Sr) used in radiological protection; and also to apply this data for the estimation of the radiation doses from strontium-89 (⁸⁹Sr) after administration to patients for the treatment of the painful bone metastases. Plasma clearance and urinary excretion of stable strontium tracers of strontium-84 (⁸⁴Sr) and strontium-86 (⁸⁶Sr) were measured in GSF-National Research Center for Environment and Health (GSF) in 13 healthy German adult subjects after intravenous injection and oral administration. The biological half-life of strontium in plasma was evaluated from 49 plasma concentration data sets following intravenous injections. This value was used to determine the transfer rates from plasma to other organs and tissues. At the same time, the long-term retention of strontium in soft tissue and whole body was constrained to be consistent with measured values available. A physiological urinary path was integrated into the biokinetic model of strontium. Parameters were estimated using our own measured urinary excretion values. Retention and excretion of strontium were modeled using compartmental transfer rates published by the International Commission on Radiological Protection (ICRP), the SENES Oak Ridge Inc. (SENES), and the Urals Research Center for Radiation Medicine (TBM). The results were compared with values calculated by applying our GSF parameters (GSF). For the dose estimation of ⁸⁹Sr, a bone metastases model (GSF-M) was developed by adding a compartment, representing the metastases, into the strontium biokinetic model. The related parameters were evaluated based on measured data available in the literature. A set of biokinetic parameters was optimized to represent not only the early plasma kinetics of strontium but also the long-term retention measured in soft tissue and whole body. The ingestion dose coefficients of ⁹⁰Sr were computed and compared with different biokinetic model parameters. The ingestion dose coefficients were calculated as 2.8 × 10⁻⁸, 2.1 × 10⁻⁸, 2.5 × 10⁻⁸ and 3.8 × 10⁻⁸ Sv Bq⁻¹ for ICRP, SENES, TBM and GSF model parameters, respectively. Moreover, organ absorbed dose for the radiopharmaceutical of ⁸⁹Sr in bone metastases therapy was estimated based on the GSF and ICRP biokinetic model parameters. The effective doses were 3.3, 1.8 and 1.2 mSv MBq⁻¹ by GSF, GSF-M, and ICRP Publication 67 model parameters, respectively, compared to the value of 3.1 mSv MBq⁻¹ reported by ICRP Publication 80. The absorbed doses of red bone marrow and bone surface, 17 and 21 mGy MBq⁻¹ calculated by GSF parameters, and 7.1 and 8.8 mGy MBq⁻¹ by GSF-M parameters, are comparable to the clinical results of 3–19 mGy MBq⁻¹ for bone marrow and 16 mGy MBq⁻¹ for bone surface. Based on the GSF-M model, the absorbed dose of ⁸⁹Sr to metastases was estimated to be 434 mGy MBq⁻¹. The strontium clearance half-life of 0.25 h from the plasma obtained in the present study is obviously faster than the value of 1.1 h recommended by ICRP. There are no significant changes for ingestion dose coefficients of ⁹⁰Sr using different model parameters. A model including the metastases was particularly developed for dose estimation of ⁸⁹Sr treatment for the pain of bone metastases.     

The induction of liver tumors by 239Pu citrate or 239PuO2 particles in the Chinese hamster

The influence of radiation dose distribution on the frequency of 239Pu-induced liver tumors was evaluated in the Chinese hamster. Different concentrations of 239Pu citrate 239PuO2 particles of known sizes were injected intravenously via the jugular vein. About 60% of the injected 239Pu citrate was deposited in the liver and 40% in the bone. The 239Pu citrate was rather uniformly distributed throughout the liver parenchyma. Injected plutonium oxide particles were taken up by the reticuloendothelial system with 90% of the body burden deposited in the liver. The 239PuO2 particles were localized in the Kupffer cells and produced nonuniform dose distributions that were dependent on particle size. There was an activity- and dose-dependent increase in the incidence of total liver parenchymal cell tumors following injection with either plutonium particles or citrate. For animals that received 14.0-, 2.7-, 0.3-, and 0.04-Gy dose to liver from 239Pu citrate the cumulative tumor incidence was 39, 32, 5, and 0%, respectively. Animals that were injected with the 0.24 micron 239PuO2 particles had doses of 42.0, 7.2, and 0.8 Gy to the liver and tumor incidences of 34, 26, and 5%, respectively. Plutonium citrate also produced hemangiosarcomas of the liver and tumors in bone and bone marrow. The latent period for liver tumor appearance in animals exposed to 239Pu citrate or 239PuO2 particles increased as the injected activity decreased. For animals injected with a similar total activity (7.4 Bq/g), the lifetime cumulative liver tumor incidence was similar for animals exposed to either 239Pu citrate (32%) or 239PuO2 (26%). There was little effect of particle size on liver tumor incidence. These data indicate that, in Chinese hamster liver, local radiation dose distribution is less important in altering tumor incidence than injected activity or average dose. However, the more uniform irradiation from 239Pu citrate administration was more effective in cancer production than the nonuniform irradiation from 239PuO2 particles.     

Dynamics of the microdistribution of 239Pu in immunocompetent structures of the rat spleen after administration of the nuclide in the nitrate form

The histoautoradiographic study has demonstrated that during the first 24 hours following the administration, plutonium is distributed diffusely and in the form of aggregates corresponding to reticular cells of marginal and brain sinuses. In addition, after 7 days on, one could observe phagocytosis of 239Pu particles and aggregates by the interdigiting reticular cells and migration thereof into follicle region where the cooperative relations occur between T- and B-lymphocytes. The absorbed radiation dose in the interdigiting cells is estimated.     

Behavior of plutonium in the body of rats following its intragastric administration in a complex with tributyl phosphate

A study was made of the distribution of plutonium-239 within the rat body after single intragastric administration thereof (1.85 MBq) in a mixture with tributyl phosphate (TBP) and as Pu(IV) nitrate at a time interval from 4 min to 512 days. It was shown that the distribution of the radionuclide was virtually the same but its absorption from the gastrointestinal tract with Pu-TBP was higher by one order of magnitude and exceeded the value recommended by ICRP for soluble plutonium compounds.     

Solubility of airborne radioactive fuel particles from the Chernobyl reactor and implication to dose

Airborne particles of nuclear fuel from the Chernobyl reactor that had been collected on air filters and stored, were characterised using in vitro dissolution tests to assess effective doses after their inhalation. As solvent, the Gamble biological fluid was used to simulate lung fluid. The solubility of the measured radionuclides decreased in the order ¹³⁷Cs>⁹⁰Sr>>²⁴¹Am^239+240Pu in the simulated lung fluid. The dissolution rate constant of e.g. ^239+249Pu ranged from 0.72 to 5.4×10^–6 g·cm^–2 d^–1 and decreased (for all nuclides) with increasing particle size as predicted from theoretical considerations. Considering the inhalation dose, decreasing dose with size and increasing doses with lower solubility may partly counterbalance each other for ¹³⁷Cs and ⁹⁰Sr. On the other hand, for ²³⁹Pu and ²⁴¹Am larger particles and associated lower solubility both change the resulting dose in the same direction towards lower values. The comparison of the experimentally determined dose coefficients with ICRP values indicates that nuclear fuel particles closely resemble type M material characteristics for ¹³⁷Cs and ⁹⁰Sr and type S material characteristics for ²³⁹Pu and ²⁴¹Am.     

Methodology Using a Portable X-Ray Fluorescence Device for On-Site and Rapid Evaluation of Heavy-Atom Contamination in Wounds: A Model Study for Application to Plutonium Contamination

Workers decommissioning the Fukushima-Daiichi nuclear power plant damaged from the Great East Japan Earthquake and resulting tsunami are at risk of injury with possible contamination from radioactive heavy atoms including actinides, such as plutonium. We propose a new methodology for on-site and rapid evaluation of heavy-atom contamination in wounds using a portable X-ray fluorescence (XRF) device. In the present study, stable lead was used as the model contaminant substitute for radioactive heavy atoms. First, the wound model was developed by placing a liquid blood phantom on an epoxy resin wound phantom contaminated with lead. Next, the correlation between the concentration of contaminant and the XRF peak intensity was formulated considering the thickness of blood exiting the wound. Methods to determine the minimum detection limit (MDL) of contaminants at any maximal equivalent dose to the wound by XRF measurement were also established. For example, in this system, at a maximal equivalent dose of 16.5 mSv to the wound and blood thickness of 0.5 mm, the MDL value for lead was 1.2 ppm (3.1 nmol). The radioactivity of ²³⁹Pu corresponding to 3.1 nmol is 1.7 kBq, which is lower than the radioactivity of ²³⁹Pu contaminating puncture wounds in previous severe accidents. In conclusion, the established methodology could be beneficial for future development of a method to evaluate plutonium contamination in wounds. Highlights: Methodology for evaluation of heavy-atom contamination in a wound was established. A portable X-ray fluorescence device enables on-site, rapid and direct evaluation. This method is expected to be used for evaluation of plutonium contamination in wounds.     

Alkaline phosphatase and transaminase activity in the liver and blood serum of rats in the late periods following combined exposure to external gamma radiation and alpha radiation from plutonium-239

A study was made of activity of alkaline phosphatase and alanine- and aspartate aminotransferase in rat liver and blood serum at remote times after external gamma-irradiation combined with internal exposure to 239Pu nitrate delivered in two chronically effective doses. The radionuclide was shown to be mainly responsible for the changes observed in activity of the enzymes under study. The degree to which the changes were manifest depended upon dose of plutonium administered.     

Self-renewal capacity of murine hemopoietic stem cells under internal contamination with239Pu and241Am

Summary The self-renewal capacity of murine pluripotent hemopoietic stem cells (CFU-S) of vertebral bone marrow was studied under conditions of short-term and long-term internal contamination with²³⁹Pu or²⁴¹Am in female mice. Measurement of the CFU-S self-renewal capacity was carried out using double transplantation assay. To evaluate the production of differentiated progeny of stem cells average erythroblast numbers/visible spleen colony and⁵⁹Fe-uptake/colony were computed. The marrow cellularity/vertebra and the number of CFU-S/vertebra were decreased and affected more by²³⁹Pu than by²⁴¹Am. The production of erythroblasts per a single CFU-S and the⁵⁹Fe-uptake/colony were reduced, similarly the numbers of secondary spleen colonies and of secondary CFU-S in primary colonies. The above changes resulting from impaired functions of surviving CFU-S were more serious with²⁴¹Am than with²³⁹Pu. The biological effects of plutonium and americium appeared independent of the phase of contamination.     

<Superscript>131</Superscript>I age-dependent inhalation dose in Southern Poland from Fukushima accident

A general method for calculating doses absorbed from isotopes released in nuclear accidents is presented. As an example, this method was used to calculate doses for inhabitants of Southern Poland due to inhalation of ¹³¹I released due to the Fukushima nuclear plant accident. ¹³¹I activity measurements in the air of that region provided the basis for the study. The proposed model is based on a complex biokinetic model for iodine merging the Leggett model developed in 2010 with the human respiratory tract and gastrointestinal tract models recommended by the International Commission on Radiological Protection (ICRP). This model is described here, and it is demonstrated that resulting dose estimates are consistent with those obtained using the ICRP methodology. Using the developed model, total doses were calculated for six age groups of both genders, for gaseous and aerosol fractions alike. The committed effective dose, H ₅₀, for an adult man reached 16 nSv, which is lower than 0.001% of the background dose. The dose for the thyroid of an adult reached 0.33 μSv, which corresponds to circa 0.0007% of the dose to the population of Southern Poland after the Chernobyl nuclear plant accident.     

Cerebrovascular diseases in nuclear workers first employed at the Mayak PA in 1948–1972

Incidence and mortality from cerebrovascular diseases (CVD) (430–438 ICD-9 codes) have been studied in a cohort of 18,763 workers first employed at the Mayak Production Association (Mayak PA) in 1948–1972 and followed up to the end of 2005. Some of the workers were exposed to external gamma-rays only while others were exposed to a mixture of external gamma-rays and internal alpha-particle radiation due to incorporated ²³⁹Pu. After adjusting for non-radiation factors, there were significantly increasing trends in CVD incidence with total absorbed dose from external gamma-rays and total absorbed dose to liver from internal alpha radiation. The CVD incidence was statistically significantly higher among workers with total absorbed external gamma-ray doses greater than 0.20 Gy compared to those exposed to lower doses; the data were consistent with a linear trend in risk with external dose. The CVD incidence was statistically significantly higher among workers with total absorbed internal alpha-radiation doses to liver from incorporated ²³⁹Pu greater than 0.025 Gy compared to those exposed to lower doses. There was no statistically significant trend in CVD mortality risk with either external gamma-ray dose or internal alpha-radiation dose to liver. The risk estimates obtained are generally compatible with those from other large occupational studies, although the incidence data point to higher risk estimates compared to those from the Japanese A-bomb survivors. Further studies of the unique cohort of Mayak workers chronically exposed to external and internal radiation will allow improving the reliability and validating the radiation safety standards for occupational and public exposure.     

Uncertainties on lung doses from inhaled plutonium

In a recent epidemiological study, Bayesian uncertainties on lung doses have been calculated to determine lung cancer risk from occupational exposures to plutonium. These calculations used a revised version of the Human Respiratory Tract Model (HRTM) published by the ICRP. In addition to the Bayesian analyses, which give probability distributions of doses, point estimates of doses (single estimates without uncertainty) were also provided for that study using the existing HRTM as it is described in ICRP Publication 66; these are to be used in a preliminary analysis of risk. To infer the differences between the point estimates and Bayesian uncertainty analyses, this paper applies the methodology to former workers of the United Kingdom Atomic Energy Authority (UKAEA), who constituted a subset of the study cohort. The resulting probability distributions of lung doses are compared with the point estimates obtained for each worker. It is shown that mean posterior lung doses are around two- to fourfold higher than point estimates and that uncertainties on doses vary over a wide range, greater than two orders of magnitude for some lung tissues. In addition, we demonstrate that uncertainties on the parameter values, rather than the model structure, are largely responsible for these effects. Of these it appears to be the parameters describing absorption from the lungs to blood that have the greatest impact on estimates of lung doses from urine bioassay. Therefore, accurate determination of the chemical form of inhaled plutonium and the absorption parameter values for these materials is important for obtaining reliable estimates of lung doses and hence risk from occupational exposures to plutonium.     

The conversion of exposures due to radon into the effective dose: the epidemiological approach

The risks and dose conversion coefficients for residential and occupational exposures due to radon were determined with applying the epidemiological risk models to ICRP representative populations. The dose conversion coefficient for residential radon was estimated with a value of 1.6 mSv year^?1 per 100 Bq m^?3 (3.6 mSv per WLM), which is significantly lower than the corresponding value derived from the biokinetic and dosimetric models. The dose conversion coefficient for occupational exposures with applying the risk models for miners was estimated with a value of 14 mSv per WLM, which is in good accordance with the results of the dosimetric models. To resolve the discrepancy regarding residential radon, the ICRP approaches for the determination of risks and doses were reviewed. It could be shown that ICRP overestimates the risk for lung cancer caused by residential radon. This can be attributed to a wrong population weighting of the radon-induced risks in its epidemiological approach. With the approach in this work, the average risks for lung cancer were determined, taking into account the age-specific risk contributions of all individuals in the population. As a result, a lower risk coefficient for residential radon was obtained. The results from the ICRP biokinetic and dosimetric models for both, the occupationally exposed working age population and the whole population exposed to residential radon, can be brought in better accordance with the corresponding results of the epidemiological approach, if the respective relative radiation detriments and a radiation-weighting factor for alpha particles of about ten are used.     

Combined prophylactic administration of riboxin and algisorbum at 239Pu intake into gastrointestinal tract of rats

The present study is devoted to the investigation of effectiveness of combined prophylactic administration of riboxin and algisorbum at 239Pu per oral intake and possible mechanisms of their interaction, and also to comparative estimation of effectiveness of combined administration of the preparations at per oral and intra peritoneal methods of riboxin introduction. The experiments have been carried out on white nonlinear rats. Riboxin (per oral and intra peritoneal) and algisorbum (per oral) have been introduced to the rats both separately and combined before per oral 239Pu introduction. Data obtained as a result of the investigation showed that combined riboxin and algisorbum introduction into gastrointestinal tract before 239PU intake lead to greater decrease in the plutonium content in the organs of deposition than single algisorbum administration. Intra peritoneal riboxin introduction reduced effectiveness of per oral algisorbum administration in plutonium binding in GI tract. Efficiency of combined riboxin and algisorbum administration in the reduction of 239Pu accumulation in organs depends on the method of riboxin introduction and develops only at per oral introduction.     

Absorbed doses and hematological shifts in dogs inhaling submicron 239Pu dioxide

In dogs breathing submicron 239Pu dioxide, the absorbed doses were determined in 12 organs and tissues where the radionuclide was deposited; the integral doses to a whole body were also determined by the sum of the exposed organs. The relationship of the hematologic changes not only with the doses for "critical" tissues but also with the integral dose was studied.     

Comparisons of the skeletal locations of putative plutonium-induced osteosarcomas in humans with those in beagle dogs and with naturally occurring tumors in both species

Osteosarcomas occur from exposures to bone-seeking, alpha-particle-emitting isotopes, particularly plutonium. The skeletal distribution of putative 239Pu-induced osteosarcomas reported in Mayak Metallurgical and Radiochemical Plutonium Plant workers is compared with those observed in canine studies, and these are compared with distributions of naturally occurring osteosarcomas in both species. In the Mayak workers, 29% and 71% of the osteosarcomas were in the peripheral and central skeleton, respectively, with the spine having the most tumors (36%). An almost identical distribution of plutonium-induced osteosarcomas was reported for dogs injected with 239Pu as young adults. This distribution of osteosarcomas is quite different from the distributions of naturally occurring osteosarcomas for both species. In the Cooperative Osteosarcoma Study Group in humans (1,736 osteosarcomas from all ages), over 91% of the tumors occurred in the peripheral skeleton. In the Mayo Clinic group of older individuals (>40 years old), over 60% of the osteosarcomas appeared in the peripheral skeleton. The distribution of naturally occurring osteosarcomas in the canine is similar to that in the adult human. The similarities of the distributions of plutonium-associated osteosarcomas in the Mayak workers with those found in experimental studies suggest that many of the reported osteosarcomas may have been associated with plutonium exposures. These results also support the experimental paradigm that plutonium osteosarcomas have a preference for well vascularized cancellous bone sites. These sites have a greater initial deposition of plutonium, but also greater turnover due to elevated bone remodeling rates.