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Biomedical subjects

R A Guilmette

Publications and source records attributed to R A Guilmette.

At least 19 recordsLinked to original sources

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.

Aerosols↗

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.

Adult↗

Comparison of absorption after inhalation and instillation of uranium octoxide.

Values for the absorption parameters were compared after inhalation or intratracheal instillation of 1.5 microm mass median aerodynamic diameter (MMAD) 233U3O8 particles into the lungs of HMT strain rats. The two sets of parameter values were similar, as were the calculated dose coefficients and predicted biokinetics for workers. Hence the inhalation and instillation techniques can probably both be used to generate values of the absorption parameters for U3O8.

Absorption↗

Scientific basis for the development of biokinetic models for radionuclide-contaminated wounds.

Radionuclide-contaminated wounds are of radiological concern because the wound provides a portal of entry of the radionuclide to the systemic circulation, and can also be a tissue at risk if sufficient dose is deposited at the wound site. Accordingly, a scientific committee established jointly by the US National Council on Radiation Protection and the International Commission on Radiological Protection has been developing an approach to describing the biokinetics of radionuclides deposited in wounds and calculating dose to the wound site. This paper focuses on the analyses, performed principally using experimental animal data, that have led to the development of a biokinetic model for deposited soluble radionuclides as well as more insoluble forms, such as colloids, particles and fragments. The available data for injected soluble materials have provided a basis for categorising 48 different elements (from Be to Cm and representing all of the chemical groups, except halogens and noble gases) into four distinct retention groups. In general, the data are adequate for developing a mechanistically based biokinetic model, whose application is exemplified for soluble radionuclides.

Animals↗

Competitive binding of Pu and Am with bone mineral and novel chelating agents.

Effective direct removal of actinides such as Pu and Am from bone in vivo has not been accomplished to date, even with the strong chelating agents CaNa3DTPA or ZnNa3DTPA. This study, using an established in vitro system, compared removal of Pu and Am bound to bone mineral by ZnNa3DTPA and 10 chelating agents designed specifically to sequester actinides, including Pu and Am. Ligands tested were tetra, hexa, and octadentate, with linear or branched backbones containing sulfocatechol [CAM(S)], hydroxycatechol [CAM(C)], hydroxipyridinone (1,2-HOPO, Me-3,2-HOPO), or hydroxamate functional groups. The wide range of Pu and Am removal exhibited by the test ligands generally agreed with their metal coordination and chemical properties. The most effective agents for Pu (100 microM concentration, 24-48 h contact) are all octadentate as follows: 3,4,3-LICAM(S) (54% unbound); 3,4,3-LICAM(C) (6.2%); 3,4,3-LI(1,2-HOPO) (3.8%); H(2,2)-(Me-3,2-HOPO) (2.2%) and DFO-(1,2-HOPO) (1.8%). The other ligands removed less than 1% of the bound Pu; and ZnNa3DTPA removed only 0.086%. The most effective ligands for Am removal (100 microM, 24-48 h contact) are as follows: octadentate H(2,2)-(Me-3,2-HOPO) (21% unbound); 3,4,3-LI(1,2-HOPO) (14.5%) and 3,4,3-LICAM(C) (5.9%); hexadentate TREN-(Me-3,2-HOPO) and TREN-(1,2-HOPO) (9.6%); and tetradentate 5-LIO(Me-3,2-HOPO) (5.2%). Am removal by ZnNa3DTPA was about 1.4%. Among the ligands presently considered for possible human use, only 3,4,3-LI(1,2-HOPO) removed potentially useful amounts of both Pu and Am from bone mineral.

Americium↗

Practical application of the ICRP Human Respiratory Tract Model.

The ICRP Publication 66 Human Respiratory Tract Model (HRTM) has been applied to calculate dose coefficients and bioassay functions using default values of parameters relating to the material and the subjects. The ICRP Task Group on Internal Dosimetry (INDOS) has developed a guidance document on application of the HRTM in situations where using specific information can improve dose assessments. INDOS is now revising the worker exposure documents (ICRP Publications 68 and 78). Application of the HRTM requires a review of the lung-to-blood absorption characteristics of inhaled radionuclides. Where appropriate, compound-specific absorption parameter values will be derived, and other compounds will be assigned to default Types using current information. Although no major changes to the HRTM are envisaged, this revision provides an opportunity for some refining and updating in the light of experience and new information.

Aerosols↗

Distribution of plutonium particles in the lungs of Mayak workers.

Lung tissues from workers at the Mayak Production Association were examined to determine the distribution of plutonium (Pu) activity in various lung compartments. Stereological sampling methods and autoradiography were used. Pu particles were identified by microscopic examination of autoradiographs and localised in one of six normal anatomic sites and two sites of fibrosis (parenchymal, non-parenchymal). Particle activity was determined by counting the number of tracks emanating from the particles. Over 50% of the Pu activity was localised in sites of fibrosis, which had significantly higher than average activity for the lung. Over 40% of the activity was in lung parenchyma. Activity in the bronchovascular interstitium was significantly lower than average. These results support the hypothesis that Pu activity is not uniformly distributed in the lung, with long-term retained particles concentrated in scars of the lung. The results may significantly affect estimates of dose from inhaled Pu.

Adult↗

Modifying the ICRP 66 dosimetry model based on results obtained from Mayak plutonium workers.

Results obtained in a study of the microscopic distribution of plutonium in the lungs of deceased Pu workers from the Mayak Production Association showed that the long-term retention of Pu was greater than predicted by the current ICRP 66 respiratory tract dosimetry model (HRTM). These data were therefore applied to the HRTM by modifying selected parameters, namely the transfer rate of Pu from the transformed state compartment and the fraction of Pu that transfers to the bound state compartment. Invoking the latter compartment into the modelling allowed a better representation of the long-term Pu retention as well as providing a convenient means of describing the workplace-specific characteristics of the different Pu aerosols found in the Mayak plant. In particular, the present model describes a significantly greater long-term retention of Pu nitrate aerosols in the lung compared with the Type M default.

Air Pollutants, Radioactive↗

Assessing the uniformity of plutonium alpha radiation dose in human lung: the Mayak experience.

Radiation-induced lung cancer risk is currently estimated based on epidemiological data from populations exposed either to relatively uniform, low-LET radiation, or from uranium miners who inhaled radon and its progeny. Inhaled alpha-emitting radionuclides (e.g. Pu and Am) produce distinctive dose patterns that may not be adequately modelled at present. Thus the distribution of Pu is being measured in formalin-fixed autopsy lung tissue from former workers at the Mayak Production Association, and which is maintained in a tissue archive at SUBI. Lungs are sampled using contemporary stereological techniques and Pu particle activities and locations are determined using quantitative autoradiography and morphological identification of lung structures. To date, > 80% of Pu particles have been observed in parenchymal lung tissues with higher concentrations being found in scar tissue. Concentrations of Pu particles in conducting airways are uniformly low, thus indicating that long-term-retained Pu particles are non-uniformly distributed in human lung, mostly in the parenchyma.

Alpha Particles↗

Effect of flow rate on particle deposition in a replica of a human nasal airway.

Charge-coupled device (CCD) imaging technology was used to observe how the spatial deposition patterns of inhaled aerosols changed as a function of rate of airflow through the airway. This technology allows the experimenter to measure local particle deposition patterns of different sized fluorescent particles at different flow rates in a full-scale multisection replica of a human nasal airway. Total particle deposition efficiencies and particle deposition patterns were measured in the nasal airway for 5.5-microm-diameter particles at constant flow rates of 10, 20, 30, and 40 L/min. Images of fluorescing particles on each plate of the exposed model were taken with a CCD camera and combined to form three-dimensional particle deposition patterns. Total particle deposition efficiency as measured with the model was found to be consistent with in vivo data. Impaction was found to be the dominant mechanism by which 5.5-microm-diameter particles deposit within the model, in agreement with published inhalation data.

Aerosols↗

Characterization of nasal spray pumps and deposition pattern in a replica of the human nasal airway.

Deposition patterns are described of a nasal spray formulation for a novel rhinovirus protease inhibitor. These patterns, which were generated from different nasal spray pumps, were characterized using a multisectional nasal airway model. A human nasal replica was made from an in vivo magnetic resonance imaging (MRI) scan of an adult male human. The nasal replica consisted of 77 acrylic plastic sections, 1.5-mm thick. Our data showed that the aerosols were deposited mainly in the anterior and turbinate regions with little passing beyond the nasopharyngeal region. Detailed deposition information from the turbinate region indicated that deposition was high toward the anterior portion where most deposition was concentrated on the inferior meatus. Spray droplets were also deposited in spots of the middle and posterior portions of the turbinate region, and this nonuniform deposition pattern may be correlated with the flow pattern. The spray angle and droplet size of the nasal spray were found to be important in influencing the deposition pattern in the nasal airway. The droplet size was determined by a laser-diffraction technique and the spray angle by high-speed photography. Larger droplets and a wider spray angle increased deposition in the anterior region of the nasal airway, which prevented more material from depositing in the turbinate region.

Administration, Inhalation↗

Review and critical analysis of available in vitro dissolution tests.

The procedures recommended in Publications 30 and 66 by ICRP for calculating radiation doses from inhaled or ingested radionuclides include classification of material on the basis of different parameters, among which transportability plays a major role, The allocation of transportable Classes or absorption Types should, whenever possible, be based on animal or human data. However, when such in vivo data are unavailable, it becomes appropriate to consider the use of other approaches, among which in vitro dissolution techniques are reasonable alternatives. This paper reviews and critically analyzes in vitro dissolution techniques that have been described historically and recommends methods shown to be useful in estimating the in vivo solubility of radioactive particles.

Administration, Inhalation↗

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.

Administration, Inhalation↗

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.

Administration, Inhalation↗

Measurement of particle deposition patterns in a human nasal airway model using a Charge Coupled Device imaging system.

Charge Coupled Device (CCD) imaging technology is being applied to measure the spatial deposition patterns of inhaled aerosols in the nasal airway. The new technology allows the experimenter to measure local particle deposition patterns of different sized fluorescent particles at variable flow rates in a full-scale multi-section replica of a human nasal airway. Images of fluorescing particles on the exposed model have been taken with a CCD camera and combined to form three-dimensional particle deposition patterns. Total particle deposition efficiencies and particle deposition patterns have been measured in the nasal airway for 6 microns diameter particles and compared with published inhalation data.

Aerosols↗

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.

Administration, Inhalation↗

A biokinetic model for 137Cs.

An improved biokinetic model for 137Cs in humans was developed based on an analysis of data obtained from individuals internally contaminated during an accident in Goiania, Brazil, and other data. Seventeen children (ten girls and seven boys 1-10 y old), ten adolescents (four females and six males), and thirty adults, (fifteen females and fifteen males contaminated in the accident in Goiânia contributed to this study. 137Cs retention was determined through periodic measurements in a whole-body counter. In addition to the data on 137Cs retention from these individuals, data from a study on the metabolism of 137Cs in immature, adult, and aged Beagle dogs and data from the literature were used in the formulation of the 137Cs biokinetic model presented. Mathematically, the retention of cesium is described by three exponential terms, and the retention model is based on a step function of body weight. When the ICRP Publication 56 model for cesium was compared to the model suggested in this paper, it was determined that the ICRP model predicts lower effective doses in 5-y-old children and higher effective doses in infants, adolescents, and adults.

Adolescent↗