A BRIEF OVERVIEW OF COMPARTMENTAL MODELING FOR INTAKE OF PLUTONIUM VIA WOUNDS.

The aim of this study is to present several approaches that have been used to model the behavior of radioactive materials (specifically Pu) in contaminated wounds. We also review some attempts by the health physics community to validate and revise the National Council on Radiation Protection and Measurements (NCRP) 156 biokinetic model for wounds, and present some general recommendations based on the review. Modeling of intake via the wound pathway is complicated because of a large array of wound characteristics (e.g. solubility and chemistry of the material, type and depth of the tissue injury, anatomical location of injury). Moreover, because a majority of the documented wound cases in humans are medically treated (excised or treated with chelation), the data to develop biokinetic models for unperturbed wound exposures are limited. Since the NCRP wound model was largely developed from animal data, it is important to continue to validate and improve the model using human data whenever plausible.

Internal dosimetry verification and validation database.

Simulated-data internal dosimetry cases for use in intercomparison exercises or as a software verification and validation tool have been published on the internet (www.lanl.gov/bayesian/software Bayesian software package II). A user may validate their internal dosimetry code or method using this simulated bioassay data. Or, the user may choose to try out the Los Alamos National Laboratory codes ID and UF, which are also supplied. A Poisson-lognormal model of data uncertainty is assumed. A collection of different possible models for each nuclide (e.g. solubility types and particle sizes) are used. For example, for 238Pu, 14 different biokinetic models or types (8 inhalation, 4 wound and 2 ingestion) are assumed. Simulated data are generated for all the assumed biokinetic models, both for incidents, where the time of intake is known, and for non-incidents, where it is not. For the dose calculations, the route of intake, but not the biokinetic model, is considered to be known. The object is to correctly calculate the known true dose from simulated data covering a period of time. A 'correct' result has been defined in two ways: (1) that the credible limits of the calculated dose include the correct dose and (2) that the calculated dose is within a factor of 2 of the correct 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.

Internal dose assessment data management system for a large population of Pu workers.

This paper describes the design and implementation of the Los Alamos National Laboratory (LANL) dose assessment (DA) data system. Dose calculations for the most important radionuclides at LANL, namely plutonium, americium, uranium and tritium, are performed through the Microsoft Access DA database. DA includes specially developed forms and macros that perform a variety of tasks, such as retrieving bioassay data, launching the FORTRAN internal dosimetry applications and displaying dose results in the form of text summaries and plots. The DA software involves the following major processes: (1) downloading of bioassay data from a remote data source, (2) editing local and remote databases, (3) setting up and carrying out internal dose calculations using the UF code or the ID code, (3) importing results of the dose calculations into local results databases, (4) producing a secondary database of 'official results' and (5) automatically creating and e-mailing reports. The software also provides summary status and reports of the pending DAs, which are useful for managing the cases in process.

In vitro dissolution study of plutonium in aerosol particles from the Mayak PA: a tool for individualised dose estimates.

Chronic inhalation of Pu particles during Mayak processing is a potential concern for workers. Of the many particle properties that affect individualised dose estimates, particle solubility in lung fluids can be most important. This study compares in vitro dissolution rates of several plutonium industrial compounds present at different stages of the Mayak processing cycle using three different solvents. The results are then used to develop values of absorption parameters for individual dose assessments. In this study, the dissolution rates of nitrate, oxide and mixed plutonium aerosols were determined using a serum ultrafiltrate stimulant (SUF), phagolysosomal simulant fluid and Ringer's solution, all using a static system. According to the results obtained with SUF, Pu nitrate is absorbed into the blood to a larger extent than predicted using model parameters currently applied for Mayak workers. Absorption into the blood of 21.5 vs. 3% of deposited nuclide as current model predicts results in underestimation of systemic burden and overestimation of the lung dose. These data are being used to provide improved retrospective dose assessments for inhaled plutonium aerosols.

Comparison of dose estimation from occupational exposure to 239Pu using different modelling approaches.

Several approaches are available for bioassay interpretation when assigning Pu doses to Mayak workers. First, a conventional approach is to apply ICRP models per se. An alternative method involves individualised fitting of bioassay data using Bayesian statistical methods. A third approach is to develop an independent dosimetry system for Mayak workers by adapting ICRP models using a dataset of available bioassay measurements for this population. Thus, a dataset of 42 former Mayak workers, who died of non-radiation effects, with both urine bioassay and post-mortem tissue data was used to test these three approaches. All three approaches proved to be adequate for bioassay and tissue interpretation, and thus for Pu dose reconstruction purposes. However, large discrepancies are observed in the resulting quantitative dose estimates. These discrepancies can, in large part, be explained by differences in the interpretation of Pu behaviour in the lungs in the context of ICRP lung model. Thus, a careful validation of Pu lung dosimetry model is needed in Mayak worker dosimetry systems.

Primary bone neoplasms in beagle dogs exposed by inhalation to aerosols of plutonium-238 dioxide.

Primary bone neoplasms developed in beagle dogs briefly exposed by inhalation to aerosols of 238PuO2. 238PuO2 was initially deposited in the respiratory tract where it was retained with a half time greater than 100 days. A portion of the 238Pu was solubilized and translocated to the liver and skeleton. Five years after exposure, 46 osteosarcomas developed in 35 of 144 exposed dogs. The cumulative absorbed radiation doses to skeleton for these dogs ranged from 210 to 830 rad. Of the 46 bone tumors, 22 originated in the vertebrae, 12 in the humeri, 6 in the pelves, and 6 in miscellaneous long and flat bones. Most of the tumors were well-differentiated sarcomas. Only 10 of the tumors metastasized; the lung was the organ most often invaded. Bone tumors were associated with lesions of radiation osteodysplasia. The number of bone tumors found in this study indicated that inhaled 238PuO2 was an effective skeletal carcinogen. The rate of solubilization in the lung and translocation to bone may be a factor in the radiation dose pattern and type and location of bone tumors that developed after inhalation of 238PuO2.

Characterization of phagolysosomal simulant fluid for study of beryllium aerosol particle dissolution.

A simulant of phagolysosomal fluid is needed for beryllium particle dissolution research because intraphagolysosomal dissolution is believed to be a necessary step in the cellular immune response associated with development of chronic beryllium disease. Thus, we refined and characterized a potassium hydrogen phthalate (KHP) buffered solution with pH 4.55, termed phagolysosomal simulant fluid (PSF), for use in a static dissolution technique. To characterize the simulant, beryllium dissolution in PSF was compared to dissolution in the J774A.1 murine cell line. The effects of ionic composition, buffer strength, and the presence of the antifungal agent alkylbenzyldimethylammonium chloride (ABDC) on beryllium dissolution in PSF were evaluated. Beryllium dissolution in PSF was not different from dissolution in the J774A.1 murine cell line (p = 0.78) or from dissolution in another simulant having the same pH but different ionic composition (p = 0.73). A buffer concentration of 0.01-M KHP did not appear adequate to maintain pH under all conditions. There was no difference between dissolution in PSF with 0.01-M KHP and 0.02-M KHP (p = 0.12). At 0.04-M KHP, beryllium dissolution was increased relative to 0.02-M KHP (p = 0.02). Use of a 0.02-M KHP buffer concentration in the standard formulation for PSF provided stability in pH without alteration of the dissolution rate. The presence of ABDC did not influence beryllium dissolution in PSF (p = 0.35). PSF appears to be a useful and appropriate model of in vitro beryllium dissolution when using a static dissolution technique. In addition, the critical approach used to evaluate and adjust the composition of PSF may serve as a framework for characterizing PSF to study dissolution of other metal and oxide particles.

In vitro dissolution of curium oxide using a phagolysosomal simulant solvent system.

Detailed study of actinide oxide behavior in alveolar macrophages (AM) in vitro is limited because of the short life span of these cells in culture. We created an in vitro dissolution system that could mimic the acidic phagolysosomal environment for the actinide and be maintained for an indefinite period so that dissolution of more insoluble materials could be measured. The dissolution system for this investigation, consisting of nine different solutions of HCl and the chelating agent diethylenetriamine pentaacetate (DTPA) in distilled water, is called the phagolysosomal simulant solvent (PSS). In this system, both the pH and the amount of DTPA were varied. We could observe the effect of altering pH within a range of 4.0-6.0 (similar to that of the phagolysosome) and the effect of the molar ratio of DTPA to curium at 1000:1, 100:1, or 10:1. We chose curium sequioxide (244Cm2O3) to validate the PSS for actinide dissolution versus that occurring in AM in vitro because it dissolves significantly in less than 1 week. The polydisperse 244Cm2O3) aerosol was generated, collected on filters, resuspended, and added to the PSS solutions and to cultured canine AM. By comparing dissolution in the two systems directly, we hoped to arrive at an optimum PSS for future dissolution studies. PSS and cell culture samples were taken daily for 7 days after exposure and tested for the solubilized curium. The amount of soluble material was determined by ultracentrifugation to separate the insoluble Cm2O3 from the soluble curium in the PSS solutions and filtration for the cell-containing material.(ABSTRACT TRUNCATED AT 250 WORDS)

Influence of dose rate on survival time for 239PuO2-induced radiation pneumonitis or pulmonary fibrosis in dogs.

Beagle dogs were exposed once or repeatedly to 0.75-microns-diameter monodisperse aerosols of 239PuO2 by pernasal inhalation. The dogs that were exposed once received alveolar depositions (+/- standard deviation) of 3.9 +/- 1.9 kBq/kg body mass and accumulated doses of 23 +/- 8 Gy to the lung before death at 5.4 +/- 1.7 years after exposure. Dogs exposed repeatedly received a total alveolar deposition of 5.3 +/- 0.9 kBq/kg body mass during 7 to 10 semiannual exposures and accumulated doses of 22 +/- 5 Gy to the lung before death at 4.9 +/- 0.7 years after first exposure. Clearance of the plutonium from the lung in the dogs exposed repeatedly was slower than in the dogs exposed once. All dogs in the repeated-exposure study and all but one dog in the single-exposure study died from radiation effects. Pulmonary fibrosis accounted for 72% of the radiation-related deaths in the single-exposure study and 87% in the repeated-exposure study. The remaining dogs died with pulmonary cancer. Based on total cumulative radiation dose, the times after exposure to death from radiation pneumonitis and pulmonary fibrosis were not significantly different for single and repeated exposures. Thus dose rate does not appear to be an important factor in predicting death from radiation pneumonitis or pulmonary fibrosis for dogs inhaling 239PuO2.

Comparative stochastic effects of inhaled alpha- and beta-particle-emitting radionuclides in beagle dogs.

The stochastic effects of inhaled, insoluble particles of alpha- or beta-particle-emitting radionuclides were compared in dogs. Male and female beagle dogs were exposed briefly by nasal inhalation to relatively insoluble aerosols of (239)PuO(2) or (144)Ce in fused aluminosilicate particles (FAP) and observed for cancer for their lifetimes. The initial lung burden and retention of each radionuclide was determined by whole-body counting of the emissions from (144)Ce-(144)Pr- or (169)Yb-labeled (239)PuO(2). Lung doses were calculated for each dog from these data. The lung doses ranged from 0.21 to 1200 Gy for (144)Ce FAP and 1.6 to 58 Gy for (239)PuO(2). Dogs with doses to the lung of about 60 Gy or greater from (144)Ce or about 2 Gy or greater from (239)PuO(2) had an increased incidence of lung carcinomas. In dogs exposed to (144)Ce FAP, three organs were targets for neoplasia: lung, tracheobronchial lymph nodes, and heart. The insoluble FAP carried to the lymph nodes draining the lung delivered high radiation doses to the nodes and adjacent heart, resulting in hemangiosarcomas of these organs. In the lung, high radiation doses induced hemangiosarcomas and carcinosarcomas. At lower doses, carcinomas of various histological patterns were induced in the lung. In dogs exposed to (239)PuO(2), the lung was the sole target organ for neoplasia. Nearly all of these neoplasms were carcinomas of various histological patterns. These results indicated that relatively low doses of alpha-particle radiation can induce pulmonary cancers, but relatively large doses of beta-particle radiation are required. In addition, inhaled beta-particle emitters can also induce cancers in lung-associated lymph nodes and heart at these larger absorbed radiation doses.

Comparative deterministic effects of inhaled, insoluble alpha- and beta-particle-emitting radionuclides in dogs.

This report compares the deterministic effects from an alpha-particle-emitting radionuclide, (239)PuO(2), and a beta-particle emitter, (144)Ce in fused aluminosilicate particles (FAP). The studies were conducted in beagle dogs of both genders exposed by inhalation to aerosols of the radionuclides. The initial lung burdens of (239)Pu and (144)Ce were determined by whole-body counting of the (169)Yb added to the plutonium aerosol during its preparation or the (144)Ce and its progeny (144)Pr. In addition, organ retention data were obtained from parallel serial sacrifice studies with the same aerosols. After exposure, the dogs were observed for health effects over their lifetime. The deterministic effects observed for both of these relatively insoluble aerosols were lymphopenia, fibrosis, atrophy of the lung-associated lymph nodes, and radiation pneumonitis. Due to the longer half-life of plutonium, the lymphopenia was more prolonged and the clinical course of the radiation pneumonitis more chronic than that resulting from cerium. The greater tissue penetration of the beta-particle emissions from the cerium resulted in more uniform dose distribution over the lung and the atria of the heart than from the alpha-particle emissions from plutonium.

Plutonium microdistribution in the lungs of Mayak workers.

The degree of nonuniform distribution of plutonium in the human lung has not been determined; thus current dosimetric models do not account for nonuniform irradiation. A better scientific basis is needed for assessing the risk of developing radiation-induced disease from inhaled alpha-particle-emitting radionuclides. We measured the distribution of plutonium activity in the lung by autoradiography and related the activity to specific compartments of the lung. The study materials were lung specimens from deceased workers employed by the Mayak Production Association. The approach to analyzing these lung samples used contemporary stereological sampling and analysis techniques together with quantitative alpha-particle autoradiography. For the first time, plutonium distribution has been quantified in the human lung. The distribution of long-term retained plutonium is nonuniform, and a significant portion of plutonium was retained in pulmonary scars. In addition, a large fraction of plutonium was present in the parenchyma, where it was retained much longer than was estimated previously. The sequestration of plutonium particles in scars would greatly reduce the radiation exposure of the critical target cells and tissues for lung cancer. Thus the prolonged retention of plutonium in lung scars may not increase the dose or risk for lung cancer.

Dosimetry of 239Pu in dogs that inhaled monodisperse aerosols of 239PuO2.

Existing data from human exposure cases and experimental animal studies on the fate and dosimetry of inhaled insoluble Pu particles are inadequate to provide a comprehensive description and evaluation of the tissues at risk from the alpha radiations of Pu. To improve our knowledge of the dosimetry of inhaled insoluble 239PuO2, this paper describes the uptake and retention of 239Pu in the tissues of dogs that received single inhalation exposures to monodisperse aerosols of 239PuO2. These data include times through 3 years after exposure. Using analytical functions fitted to each tissue data set, 1100-day radiation doses were calculated for lung, liver, skeleton, kidney, spleen, and tracheobronchial, mediastinal, sternal, hepatic, mandibular, and retropharyngeal lymph nodes. The dosimetry results suggest that the lung and lymph nodes associated with lymphatic drainage of the respiratory tract are the principal sites of alpha irradiation. However, the doses for the different respiratory tract lymph nodes vary by a factor of 2000, suggesting that assuming equivalent doses to respiratory tract lymph nodes is not appropriate. Other tissues receive radiation doses also but at levels one to three orders of magnitude less than the lung. Particle size dependence on uptake and retention was noted for the skeleton, mediastinal lymph nodes, hepatic lymph nodes, retropharyngeal lymph nodes, and mandibular lymph nodes.

Distribution and biological effects of inhaled 239Pu(NO3)4 in cynomolgus monkeys.

Twenty male cynomolgus monkeys were exposed by inhalation either to an aerosol of 239Pu(NO3)4 to produce projected initial lung burdens of either 40, 10, or 4 kBq or to a carrier aerosol as a control. Animals died or were sacrificed at 0.01, 1, 3, 6, 12, 24, 40, and 99 months after inhalation, and the distribution and biological effects of the 239Pu were determined. The 239Pu cleared efficiently from the lungs so that less than 0.05 kBq remained at 99 months after exposure to 40 kBq. Total skeletal 239Pu activity was nearly constant after the first year, but the fraction of the body burden in skeleton at sacrifice increased with time up to 99 months because of clearance from other organs. Plutonium in the liver increased to a peak at 1 year and then decreased to about 10% of the peak value at 99 months. Plutonium in the testes was localized in the interstitial tissue with only 0.01 to 0.002% of the projected lung burden remaining in testes at 99 months after inhalation. Three animals exposed to 40 kBq of 239Pu died of radiation-related pulmonary pneumonitis and fibrosis. A primary papillary adenocarcinoma of the lung was identified in one animal exposed to 40 kBq initial lung burden and sacrificed 99 months after inhalation. The frequency of chromosome aberrations in blood lymphocytes was significantly elevated only in monkeys with projected deposits of 40 kBq of 239Pu. There was no change in aberration frequency in other exposure groups as a function of inhaled activity, time after exposure, or calculated total dose to the lungs. Only in monkeys that had marked radiation-induced pathological changes in the lung did the frequency of chromosome-type aberrations increase significantly, to a value about twice the control level. In cynomolgus monkeys, chromosome aberration frequency in blood lymphocytes is not a good indicator of radiation dose or damage from inhaled soluble plutonium.

Cardiopulmonary function of dogs with plutonium-induced chronic lung injury.

Beagle dogs had signs of restrictive lung disease 1 to 5 years after exposure by inhalation to 239PuO2 aerosols. The 239PuO2 aerosols were monodisperse with activity median aerodynamic diameters of 0.75, 1.5, or 3.0 microns. The plutonium particles produced protracted alpha irradiation of the lungs. Ten dogs had specific initial pulmonary burdens (IPB) of 330 to 4,100 kBq of 239PuO2/kg of body mass. The average onset time of clinical signs of lung injury was 3 years after exposure; the average time from the onset of signs until cardiorespiratory function evaluation was 5.5 years. A second group of 10 dogs had IPB of 110 to 2000 kBq of 239Pu/kg of body mass but no signs of lung injury. A third group of 10 dogs, not exposed to 239Pu, were matched for age and sex. Cardiopulmonary function tests were performed. Only the dogs in group I with signs of lung injury had a mild respiratory function disorder consisting of smaller lung volumes, reduced compliance, increased respiratory frequency and minute volume, and reduced carbon monoxide diffusing capacity. Cardiac function of all three groups was similar. These findings indicate that alpha irradiation of the lungs of man could produce restrictive lung disease at long times after initial exposure.

Dose responses from inhaled monodisperse aerosols of 244Cm2O3 in the lung, liver and skeleton of F344 rats and comparison with 239PuO2.

The purpose of this study was to obtain information on the alpha-particle dose-response relationship of 244Cm in rats. Rats were exposed briefly by inhalation to graded levels of monodisperse aerosols of 244Cm2O3 heat-treated at 1150 degrees C. The initial lung burden (ILB) of each animal was determined by the use of the gamma-ray-emitting radionuclide 243Cm in the aerosols. Seven groups of 84-day-old F344/Crl rats (a total of 637 males and 645 females) were exposed once to 244Cm2O3 or sham-exposed to filtered ambient air. Mean ILBs of all rats per group ranged from 0.51 +/- 0.17 (+/-SD) to 240 +/- 82 kBq kg-1 body weight. Mean lifetime alpha-particle doses to the lungs per group ranged from 0.20 +/- 0.069 (+/-SD) to 36 +/- 6.5 Gy. After death, each rat was radiographed and necropsied. Dose-related increases occurred in incidences of benign and malignant lung neoplasms, except for the groups of rats with higher mean ILBs that were examined histologically (98 +/- 18 and 240 +/- 77 kBq kg-1 body weight) in which survival was markedly decreased. Also, average alpha-particle doses of 0.0014 +/- 0.00058 (+/-SD) to 0.17 +/- 0.091 Gy and 0.18 +/- 0.007 to 1.6 +/- 1.1 Gy were also absorbed by the liver and skeleton, respectively, in the rats in the different exposure groups. Primary liver neoplasms occurred in several rats. However, the incidence of these lesions was not related to dose. Increased incidences of bone neoplasms occurred only in rats receiving higher doses to the skeleton. Excess numbers of rats with lung neoplasms per 10(4) Gy to the lung per group ranged from 760 +/- 430 (+/- SE) at a mean dose of 0.48 Gy to 84 +/- 16 at a mean dose of 37 Gy. Risk factors for the lowest and highest ILB kg-1 body weight groups were not considered reliable because of large errors associated with these calculations and the life-span shortening in the highest ILB kg-1 group. Inhaled 244Cm2O3 appeared to be about 50% less effective as a lung carcinogen in rats compared to 239PuO2 at similar doses.

Toxicity of inhaled plutonium dioxide in beagle dogs.

This study was conducted to determine the biological effects of inhaled 238PuO2 over the life spans of 144 beagle dogs. The dogs inhaled one of two sizes of monodisperse aerosols of 238PuO2 to achieve graded levels of initial lung burden (ILB). The aerosols also contained 169Yb to provide a gamma-ray-emitting label for the 238Pu inhaled by each dog. Excreta were collected periodically over each dog's life span to estimate plutonium excretion; at death, the tissues were analyzed radiochemically for plutonium activity. The tissue content and the amount of plutonium excreted were used to estimate the ILB. These data for each dog were used in a dosimetry model to estimate tissue doses. The lung, skeleton and liver received the highest alpha-particle doses, ranging from 0.16-68 Gy for the lung, 0.08-8.7 Gy for the skeleton and 0.18-19 for the liver. At death all dogs were necropsied, and all organs and lesions were sampled and examined by histopathology. Findings of non-neoplastic changes included neutropenia and lymphopenia that developed in a dose-related fashion soon after inhalation exposure. These effects persisted for up to 5 years in some animals, but no other health effects could be related to the blood changes observed. Radiation pneumonitis was observed among the dogs with the highest ILBs. Deaths from radiation pneumonitis occurred from 1.5 to 5.4 years after exposure. Tumors of the lung, skeleton and liver occurred beginning at about 3 years after exposure. Bone tumors found in 93 dogs were the most common cause of death. Lung tumors found in 46 dogs were the second most common cause of death. Liver tumors, which were found in 20 dogs but were the cause of death in only two dogs, occurred later than the tumors in bone and lung. Tumors in these three organs often occurred in the same animal and were competing causes of death. These findings in dogs suggest that similar dose-related biological effects could be expected in humans accidentally exposed to 238PuO2.

Statistical modeling of carcinogenic risks in dogs that inhaled 238PuO2.

Combined analyses of data on 260 life-span beagle dogs that inhaled 238PuO2 at the Inhalation Toxicology Research Institute (ITRI) and at Pacific Northwest National Laboratory (PNNL) were conducted. The hazard functions (age-specific risks) for incidence of lung, bone and liver tumors were modeled as a function of cumulative radiation dose, and estimates of lifetime risks based on the combined data were developed. For lung tumors, linear-quadratic functions provided an adequate fit to the data from both laboratories, and linear functions provided an adequate fit when analyses were restricted to doses less than 20 Gy. The estimated risk coefficients for these functions were significantly larger when based on ITRI data compared to PNNL data, and dosimetry biases are a possible explanation for this difference. There was also evidence that the bone tumor response functions differed for the two laboratories, although these differences occurred primarily at high doses. These functions were clearly nonlinear (even when restricted to average skeletal doses less than 1 Gy), and evidence of radiation-induced bone tumors was found for doses less than 0.5 Gy in both laboratories. Liver tumor risks were similar for the two laboratories, and linear functions provided an adequate fit to these data. Lifetime risk estimates for lung and bone tumors derived from these data had wide confidence intervals, but were consistent with estimates currently used in radiation protection. The dog-based lifetime liver tumor risk estimate was an order of magnitude larger than that used in radiation protection, but the latter also carries large uncertainties. The application of common statistical methodology to data from two studies has allowed the identification of differences in these studies and has provided a basis for common risk estimates based on both data sets.

Decorporation therapy for inhaled plutonium nitrate using repeatedly and continuously administered DTPA.

Decorporation therapy is the only known effective method of reducing the radiation dose to persons accidentally contaminated internally with radionuclides. Deposition of actinides in bone must be minimized because osteosarcoma appears to be the most likely pathological effect arising from systemic exposure. In previous studies, beagle dogs inhaled moderately soluble Am and Cm oxide aerosols and were then treated with diethylenetriaminepentaacetic acid (DTPA), either by repeated intravenous injection or by continuous infusion. The latter therapy was more effective in removing the actinides from the body. In this complementary study, dogs inhaled a polydisperse aerosol of 238Pu(NO3)4 and were treated as before using a single initial injection of CaDTPA (30 mumol kg-1) followed with either repeated intravenous injections of ZnDTPA (30 mumol kg-1 injection) or with subcutaneous infusion of ZnDTPA (30 or 120 mumol kg-1 day-1). Each treatment regimen commenced at 1 h after exposure and continued throughout 64 days, whereupon all animals were killed, and tissue samples and collected excreta samples were analysed radiochemically for their Pu contents. Unlike the results of previous studies with Am and Cm, in which the actinide dissolved in vivo over periods of many days to weeks, no significant differences in decorporation efficiency of 238Pu were noted for the three different DTPA-treated groups. All treatments removed about 85% of the initial pulmonary burden (IPB) of 238Pu compared with 24% IPB excreted by the saline-treated control dogs. The lack of additional effectiveness of the continuously infused DTPA was attributed to the high, initial in vivo solubility of the Pu nitrate aerosol used in this study. This resulted in a relatively rapid systemic uptake of Pu and translocation to liver, skeleton, and muscle/connective tissue, where it was less available to the longer-term action of DTPA.