Low-energy cross-section calculations of single molecules by electron impact: a classical Monte Carlo transport approach with quantum mechanical description.

The present state of modeling radio-induced effects at the cellular level does not account for the microscopic inhomogeneity of the nucleus from the non-aqueous contents (i.e. proteins, DNA) by approximating the entire cellular nucleus as a homogenous medium of water. Charged particle track-structure calculations utilizing this approximation are therefore neglecting to account for approximately 30% of the molecular variation within the nucleus. To truly understand what happens when biological matter is irradiated, charged particle track-structure calculations need detailed knowledge of the secondary electron cascade, resulting from interactions with not only the primary biological component-water--but also the non-aqueous contents, down to very low energies. This paper presents our work on a generic approach for calculating low-energy interaction cross-sections between incident charged particles and individual molecules. The purpose of our work is to develop a self-consistent computational method for predicting molecule-specific interaction cross-sections, such as the component molecules of DNA and proteins (i.e. nucleotides and amino acids), in the very low-energy regime. These results would then be applied in a track-structure code and thereby reduce the homogenous water approximation. The present methodology-inspired by seeking a combination of the accuracy of quantum mechanics and the scalability, robustness, and flexibility of Monte Carlo methods-begins with the calculation of a solution to the many-body Schrödinger equation and proceeds to use Monte Carlo methods to calculate the perturbations in the internal electron field to determine the interaction processes, such as ionization and excitation. As a test of our model, the approach is applied to a water molecule in the same method as it would be applied to a nucleotide or amino acid and compared with the low-energy cross-sections from the GEANT4-DNA physics package of the Geant4 simulation toolkit for the energy ranges of 7 eV to 1 keV.

Molecular imaging of small animals with a triple-head SPECT system using pinhole collimation.

Pinhole collimation yields high sensitivity when the distance from the object to the aperture is small, as in the case of imaging small animals. Fine-resolution images may be obtained when the magnification is large since this mitigates the effect of detector resolution. Large magnifications in pinhole single-photon emission computed tomography (SPECT) may be obtained by using a collimator whose focal length is many times the radius of rotation. This may be achieved without truncation if the gamma camera is large. We describe a commercially available clinical scanner mated with pinhole collimation and an external linear stage. The pinhole collimation gives high magnification. The linear stage allows for helical pinhole SPECT. We have used the system to image radiolabeled molecules in phantoms and small animals.

Long term response in a patient with neoplastic meningitis secondary to melanoma treated with (131)I-radiolabeled antichondroitin proteoglycan sulfate Mel-14 F(ab')(2): a case study.

Even with novel chemotherapeutic agents and external beam radiation therapy, the prognosis of neoplastic meningitis secondary to malignant melanoma is still dismal. The authors report a case study of a 46-year-old white female who presented with progressive hearing loss, severe headaches, nausea, vomiting, and a rapid decline in neurologic status. She was referred to Duke University Medical Center after conventional chemotherapy for malignant melanoma failed. She was enrolled in a Phase I trial of (131)I-labeled monoclonal antibody Mel-14 F(ab')(2) fragment administered intrathecally. Within a year after her treatment, she recovered, having a normal neurologic exam except for residual bilateral hearing loss. The authors discuss dosimetry, preclinical, and clinical studies conducted with Mel-14 F(ab')(2) and introduce a potentially promising therapy option in the treatment of neoplastic meningitis in patients with malignant melanoma. Currently, the patient remains neurologically normal except for a mild bilateral hearing loss more than 4 years after treatment and has no radiographic evidence of neoplastic meningitis.

Phase I trial results of iodine-131-labeled antitenascin monoclonal antibody 81C6 treatment of patients with newly diagnosed malignant gliomas.

PURPOSE: To determine the maximum-tolerated dose (MTD) of iodine-131 ((131)I)-labeled 81C6 antitenascin monoclonal antibody (mAb) administered clinically into surgically created resection cavities (SCRCs) in malignant glioma patients and to identify any objective responses with this treatment. PATIENTS AND METHODS: In this phase I trial, newly diagnosed patients with malignant gliomas with no prior external-beam therapy or chemotherapy were treated with a single injection of (131)I-labeled 81C6 through a Rickham reservoir into the resection cavity. The initial dose was 20 mCi and escalation was in 20-mCi increments. Patients were observed for toxicity and response until death or for a minimum of 1 year after treatment. RESULTS: We treated 42 patients with (131)I-labeled 81C6 mAb in administered doses up to 180 mCi. Dose-limiting toxicity was observed at doses greater than 120 mCi and consisted of delayed neurotoxicity. None of the patients developed major hematologic toxicity. Median survival for patients with glioblastoma multiforme and for all patients was 69 and 79 weeks, respectively. CONCLUSION: The MTD for administration of (131)I-labeled 81C6 into the SCRC of newly diagnosed patients with no prior radiation therapy or chemotherapy was 120 mCi. Dose-limiting toxicity was delayed neurologic toxicity. We are encouraged by the survival and toxicity and by the low 2.5% prevalence of debulking surgery for symptomatic radiation necrosis.

Red marrow dosimetry for radiolabeled antibodies that bind to marrow, bone, or blood components.

Hematologic toxicity limits the radioactivity that may be administered for radiolabeled antibody therapy. This work examines approaches for obtaining biodistribution data and performing dosimetry when the administered antibody is known to bind to a cellular component of blood, bone, or marrow. Marrow dosimetry in this case is more difficult because the kinetics of antibody clearance from the blood cannot be related to the marrow. Several approaches for obtaining antibody kinetics in the marrow are examined and evaluated. The absorbed fractions and S factors that should be used in performing marrow dosimetry are also examined and the effect of including greater anatomical detail is considered. The radiobiology of the red marrow is briefly reviewed. Recommendations for performing marrow dosimetry when the antibody binds to the marrow are provided.

Exposure of human osteosarcoma and bone marrow cells to tumour-targeted alpha-particles and gamma-irradiation: analysis of cell survival and microdosimetry.

PURPOSE: This study was designed to compare the cytotoxic effects of an alpha-emitting radioimmunoconjugate, which binds to osteosarcoma but not to bone marrow cells, with those of external gamma-irradiation. MATERIALS AND METHODS: The human osteosarcoma cell line, OHS-s1, and mononuclear cells from bone marrow (BM) harvested from healthy donors, were used for these experiments. Cells in suspension were added to various activity concentrations of the anti-osteosarcoma monoclonal antibody TP-3 radiolabelled with 211At. Following incubation for 1 h, unbound radioactivity was washed off and cell survival was determined from clonogenic assays. Microdosimetry was calculated based on binding and retention kinetics of 211At to the cells, as well as cellular and nuclear diameters. For comparison, cell suspensions were irradiated with a single dose of 60Co gamma-rays. RESULTS: 211At-labelled TP-3 showed heterogeneous binding to OHS-s1 cells, with a considerable variation among experiments. About 78% of the initially bound 211At decayed while associated with the OHS-s1 cells. D0 values estimated by microdosimetry were 0.33 (0.22-0.48, range) Gy and 1.18 (0.89-1.89) Gy for OHS-s1 and BM cells, respectively, whereas D0 values after external beam irradiation were 0.86+/-0.07Gy and 1.71+/-0.22Gy. The relative biological effectiveness (RBE) of 211At-labelled TP-3 at 37% survival was 3.43 for OHS-s1 and 1.55 for BM. CONCLUSIONS: High-LET targeted alpha-particle exposure killed osteosarcoma cells more effectively than bone marrow cells, although heterogeneous antigen expression among these tumour cells limited the magnitude of this effect.

Dosimetry and dose-response relationships in newly diagnosed patients with malignant gliomas treated with iodine-131-labeled anti-tenascin monoclonal antibody 81C6 therapy.

PURPOSE: The objective of this study was to perform the dosimetry and evaluate the dose-response relationships in newly diagnosed patients with malignant brain tumors treated by direct injections of (131)I-labeled 81C6 monoclonal antibody (MAb) into surgically created resection cavities (SCRCs). METHODS AND MATERIALS: Absorbed doses to the 2-cm-thick shell as measured from the margins of the resection cavity interface were estimated for 42 patients with primary brain tumors. MR images were used to assess the enhanced-rim volume as a function of time after radiolabeled MAb therapy. Biopsy samples were obtained from 15 patients and 1 autopsy. RESULTS: The average absorbed dose [range] to the 2-cm shell region was 32 [3-59] Gy. For the endpoint of minimal time to MR contrast enhancement, the optimal absorbed dose and initial dose-rate were 43 +/- 16 Gy and 0. 41 +/- 0.10 Gy/h, respectively. There was a correlation between the absorbed dose and dose rate to the shell region and biopsy outcome (tumor recurrence, radionecrosis, and tumor recurrence and/or radionecrosis). In this Phase I study, the maximum tolerated dose (MTD) was 120 mCi. At this MTD, the estimated average absorbed dose and initial dose rate to the 2-cm shell were 41 [9-89] Gy and 0.51 [0.24-1.13] Gy/h, respectively. These values are in agreement with the optimal values based on the time to MR lesion rim enhancement. CONCLUSIONS: The average absorbed dose to the 2-cm shell region varied considerably and mainly depended on cavity volume. In future clinical trials, the administered activity of (131)I-labeled 81C6 MAb may be adjusted based on cavity volume in order to deliver the optimal absorbed dose of 43 Gy rather than giving a fixed administered activity.

Radiotoxicity of systemically administered 211At-labeled human/mouse chimeric monoclonal antibody: a long-term survival study with histologic analysis.

PURPOSE: The antitenascin human/mouse chimeric monoclonal antibody labeled with the alpha-particle-emitting radionuclide 211At is of interest as an endoradiotherapeutic agent for the treatment of brain tumors. To facilitate the investigation of 211At-labeled chimeric 81C6 in patients, the long-term radiotoxicity of this radiopharmaceutical has been evaluated. METHODS AND MATERIALS: Antibody labeling was performed using N-succinimidyl 3-[211At]astato-benzoate. After an initial dose-finding experiment, a second toxicity study was carried out at 4 dose levels in groups of 30 nonthyroid blocked B6C3F1 mice per group (15 males, 15 females). Male mice received either saline or 15-81 kBq/g and females received either saline or 16-83 kBq/g of 211At-labeled antibody. Ten animals (5 males, 5 females) were followed for 6 months and the remainder for 1 year. RESULTS: The lethal dose in 10% of animals (LD10) for 211At-labeled chimeric 81C6 was 46 kBq/g in females and 102 kBq/g in males. Toxic effects--perivascular fibrosis of the intraventricular septum of the heart, bone marrow suppression, splenic white pulp atrophy, and spermatic maturational delay--generally were confined to a few animals receiving the highest doses of labeled antibody. CONCLUSIONS: The LD10 of 211At-labeled chimeric 81C6 in this mouse strain was about half that of [211At]astatide. These results establish the preclinical maximum tolerated dose of 211At-labeled chimeric 81C6 and define in the mouse the target organs for toxicity. These studies will be useful for determining starting doses for clinical studies with 211At-labeled chimeric 81C6.

211At- and 131I-labeled bisphosphonates with high in vivo stability and bone accumulation.

UNLABELLED: Bisphosphonates were synthesized for use as carriers for astatine and iodine radioisotopes to target bone neoplasms. METHODS: Radiohalogenated activated esters were coupled to the amino group in the side chain of the bisphosphonate. The bisphosphonate 3-amino-1-hydroxypropylidene bisphosphonate was combined with four different acylation agents: N-succinimidyl 3-[211At]astatobenzoate, N-succinimidyl 3-[131I]iodobenzoate, N-succinimidyl-5-[211At]astato-3-pyridinecarboxylate and N-succinimidyl-5-[131I]iodo-5-pyridinecarboxylate. The products, 3-[131I]iodobenzamide-N-3-hydroxypropylidene-3,3-bisphosphonate (IBPB), 3-[211At]astato-benzamide-N-3-hydroxypropylidene-3,3-bisphosphonat e (ABPB), 5-[131I]iodopyridine-3-amide-N-3-hydroxypropylidene-3,3-bisphospho nate (IPPB) and 5-[211At]astatopyridine-3-amide-N-3-hydroxypropylidene-3,3-bisphos phonate (APPB), were injected intravenously into Balb/c mice. MIRD and Monte Carlo methods were used on the basis of cumulated activity calculated from biodistribution data to estimate dose to organs and bone segments. RESULTS: All 131I- and 211At-labeled analogs were strongly incorporated into osseous tissue and retained there at stable levels, while a rapid clearance from blood was observed. The bone uptake was found to be similar for 211At- and 131I-labeled bisphosphonate when compared in paired label experiments. Bone uptake and bone-to-tissue ratios were better for IBPB compared with IPPB, and ABPB compared with APPB. All four compounds appeared to be highly resistant to in vivo dehalogenation as indicated by low uptake of 131I/211At in the thyroid gland and stomach. According to dosimetric estimates, the bone surface-to-bone marrow ratio was three times higher with 211At than with 131I. CONCLUSION: Both the beta-particle- and alpha-particle-emitting compounds showed high in vivo stability and excellent affinity for osseous tissue. Further preclinical evaluation is therefore warranted.

Dosimetry of 131I-labeled 81C6 monoclonal antibody administered into surgically created resection cavities in patients with malignant brain tumors.

UNLABELLED: The objective of this study was to perform the dosimetry of 131I-labeled 81C6 monoclonal antibody (MAb) in patients with recurrent malignant brain tumors, treated by direct injections of MAb into surgically created resection cavities (SCRCs). METHODS: Absorbed dose estimates were performed for nine patients. Dosimetry was performed retrospectively using probe counts (during patient isolation) and whole-body and SPECT images thereafter. Absorbed doses were calculated for the SCRC interface and for regions of interest (ROIs) 1 and 2 cm thick, measured from the margins of cavity interface. Also, mean absorbed doses were calculated for normal brain, liver, spleen, thyroid gland, stomach, bone marrow and whole body. The average residence time for the SCRC was 111 h (65-200h). RESULTS: The average absorbed dose per unit injected activity (range) to the SCRC interface and ROIs 1 and 2 cm thick from the cavity interface were 31.9 (7.8-84.2), 1.9 (0.7-3.6) and 1.0 (0.4-1.8) cGy/MBq, respectively. Average absorbed doses per unit administered activity to brain, liver, spleen, thyroid, stomach, bone marrow and whole body were 0.18, 0.03, 0.08, 0.05, 0.02, 0.02 and 0.01 cGy/MBq, respectively. The high absorbed dose delivered to the SCRC interface may have produced an increase in cavity volume independent of tumor progression. CONCLUSION: At the maximum tolerated dose of 3700 MBq 131I-labeled 81C6 MAb, the absorbed doses to the SCRC interface and ROIs of 1 and 2 cm thickness were estimated to be 1180, 71 and 39 Gy, respectively. The estimated average absorbed dose to the brain was 6.5 Gy. There was no neurological toxicity and minimal hematologic toxicity at this maximum tolerated administration level.

Migration of human dendritic cells after injection in patients with metastatic malignancies.

Present clinical studies of active immunotherapy for malignancies using dendritic cells (DCs) require elucidation of the sites where DCs localize after injection. We evaluated the pattern of distribution of in vitro-generated, antigen-loaded, human DCs labeled with indium-111 oxyquinoline after i.v., s.c., and intradermal injection. Whereas the DCs injected i.v. localized in the lungs and then redistributed to the liver, spleen, and bone marrow, they were not detected in lymph nodes or tumors. A small percentage of DCs injected intradermally migrated rapidly to the regional lymphatics in some individuals. No lymph node activity was detected after s.c. injection. Our results demonstrate that DC distribution to sites of lymphoid tissue is dramatically affected by the mode of administration.

Locally increased uptake of fluorine-18-fluorodeoxyglucose after intracavitary administration of iodine-131-labeled antibody for primary brain tumors.

UNLABELLED: After the intracavitary administration of 131I-labeled monoclonal antibody for treatment of primary brain tumors after surgical resection, a persistent rim of 18F-fluorodeoxyglucose (FDG) accumulation surrounding the cavity can be observed on PET. This rim, although it accumulates more FDG than adjacent normal brain tissue, is not necessarily associated with tumor. In our study, we examine the characteristics of the rim that indicate persistent tumor and tumor progression. METHODS: Sequential PET studies obtained after treatment in 10 patients were reviewed and the results correlated with dosimetry and post-treatment histologic diagnoses. RESULTS: The rim of FDG accumulation was seen on the first post-treatment scan obtained 1-3 mo after therapy and persisted unchanged over the 2-26 mo follow-up period. Pathologically, the nonmalignant rim was associated with marked increase of macrophage infiltrates. Nodularity of the rim was associated with tumor. CONCLUSION: Our study demonstrates that a rim of FDG accumulation is seen after intracavitary administration of 131I-labeled monoclonal antibody therapy independent of the presence of malignant disease. Malignant recurrence is suggested by the development of new nodularity in the rim of FDG accumulation.

Iodine-131-labeled antitenascin monoclonal antibody 81C6 treatment of patients with recurrent malignant gliomas: phase I trial results.

PURPOSE: To determine the maximum-tolerated dose (MTD) of iodine 131 (131I)-labeled 81C6 monoclonal antibody (mAb) in brain tumor patients with surgically created resection cavities (SCRCs) and to identify any objective responses to this treatment. METHODS: In this phase I trial, eligible patients were treated with a single injection of 131I-labeled 81C6. Cohorts of three to six patients were treated with escalating dosages of 131I (starting dose of 20 mCi with a 20-mCi escalation in subsequent cohorts) administered through an Ommaya reservoir in the SCRC. Patients were followed up for toxicity and response until death or for a minimum of 1 year after treatment. The SCRC patients, who were previously irradiated, were followed up without additional treatment unless progressive disease was identified. RESULTS: We administered 36 treatments of 131I doses up to 120 mCi to 34 previously irradiated patients with recurrent or metastatic brain tumors. Dose-limiting toxicity was reached at 120 mCi and was limited to neurologic or hematologic toxicity. None of the patients treated with less than 120 mCi developed significant neurologic toxicity; one patient developed major hematologic toxicity (MHT). The estimated median survival for patients with glioblastoma multiforme (GBM) and for all patients was 56 and 60 weeks, respectively. CONCLUSION: The MTD for administration of 131I-labeled 81C6 into the SCRCs of previously irradiated patients with recurrent primary or metastatic brain tumors was 100 mCi. The dose-limiting toxicity was neurologic toxicity. We are encouraged by the minimal toxicity and survival in this phase I trial. Radiolabeled mAbs may improve the current therapy for brain tumor patients.

The cytotoxicity and microdosimetry of astatine-211-labeled chimeric monoclonal antibodies in human glioma and melanoma cells in vitro.

The cytotoxicity of alpha-particle-emitting endoradiotherapeutic compounds is of increasing interest because clinical evaluation of these potential therapeutic agents is commencing. Astatine-211 is a radionuclide with a 7.2-h half-life that emits 5.87 and 7.45 MeV alpha particles. In the present work, we have investigated the in vitro cytotoxicity of 211At-labeled chimeric monoclonal antibodies (mAbs) in monolayers of D-247 MG human glioma cells and SK-MEL-28 human melanoma cells. The mAbs studied were 81C6, reactive with the extracellular matrix antigen tenascin, Mel-14, directed against the cell membrane antigen proteoglycan chondroitin sulfate, and a nonspecific control mAb, TPS3.2. Cell uptake increased as a function of activity concentration after a 1-h exposure to the 211At-labeled mAbs. The retention of activity was also measured to calculate cumulative activity associated with the cells and the medium. The clonogenic survival as a function of activity concentration was linear in all cases with no detectable shoulder. Microdosimetric analyses were performed based on measured cell geometry, cumulative activity and Monte Carlo transport of alpha particles. Using 18 kBq/ml activity concentration and 1 h of incubation, a two to five times higher activity bound to the microcolonies was found for the specific mAbs compared to the nonspecific mAb. These calculations indicated that a survival fraction of 0.37 was achieved with 0.24-0.28 Gy for D-247 MG cells and 0.27-0.29 Gy for SK-MEL-28 cells. The microdosimetric cell sensitivity, z0, for D-247 MG cells was significantly lower than for SK-MEL-28 cells (0.08 compared to 0.15 Gy). For both cell lines, reduction in survival to 0.37 required an average of only 1-2 alpha-particle hits to the cell nucleus.

Microdosimetry of astatine-211 using histological images: application to bone marrow.

A method is presented for calculating the small-scale dosimetry of 211At in red bone marrow using chord-length distributions obtained from digitized histological images. This study used histological samples of bone marrow from beagle dogs to convey morphological information about cell conglomerations within bone marrow. Two 211At activity distributions were considered within the extracellular fluid and the surface of red bone marrow cells. Results confirmed the influence of cell conglomeration and activity distribution in determining the microdosimetry of red bone marrow. Average S* values of 1.6 x 10(-9) and 1.90 x 10(-9) Gy g Bq(-1) s(-1) were calculated for activity distributions located within the extracellular fluid and the surface of red bone marrow cells, respectively. The cumulated activity required to reduce survival probability to 0.37 also was calculated as a function of cell sensitivity for both activity distributions. The activity distribution on the cell surface resulted in a higher cell-killing efficiency, requiring a lower activity concentration of approximately 25% when compared with activity located in the extracellular fluid. Of relevance to potential clinical studies with 211At, the probability for zero hits for red bone marrow cells was > 10% for cumulated activities of less than 5.5 x 10(8) Bq s g(-1) in bone marrow.

Patient-specific dosimetry of indium-111- and yttrium-90-labeled monoclonal antibody CC49.

UNLABELLED: The objective of this work was to develop patient-specific dosimetry for patients with metastatic gastrointestinal tract cancers who received 111In-CC49 IgG for imaging before therapy with 90Y-CC49 IgG. METHODS: Whole-body imaging of 12 patients, who received 111-185 MBq (3-5 mCi) of 111In-CC49, commenced in < 2 hr postinfusion and was continued daily for 4-5 days. SPECT data were acquired at 24 and 72 hr to determine the range of 111In-CC49 activity concentrations in tumors and normal organs. Time-activity curves were generated from the image data and scaled from 111In-CC49 to 90Y-CC49 for dosimetric purposes. Absorbed-dose calculations for 90Y-CC49 included the mean and range in tumor and normal organs. Computed 90Y-CC49 activity concentrations were compared with measurements on 10 needle biopsies of normal liver and four tumor biopsies. RESULTS: In 9 of 10 normal liver samples, the range of computed 90Y-CC49 activity concentrations bracketed measured values. This was also the case for 3 of 4 tumor biopsies. Absorbed-dose calculations for 90Y-CC49 were based on patients' images and activities in tissue samples and, hence, were patient-specific. CONCLUSION: For the radiolabeled antibody preparations used in this study, quantitative imaging of 111In-CC49 provided the data required for 90Y-CC49 dosimetry. The range of activities in patients' SPECT images was determined for a meaningful comparison of measured and computed values. Knowledge of activity distributions in tumors and normal organs was essential for computing mean values and ranges of absorbed dose and provided a more complete description of the absorbed dose from 90Y-CC49 than was possible with planar methods.

Patient-specific dosimetry using quantitative SPECT imaging and three-dimensional discrete Fourier transform convolution.

UNLABELLED: The objective of this study was to develop a three-dimensional discrete Fourier transform (3D-DFT) convolution method to perform the dosimetry for 131I-labeled antibodies in soft tissues. METHODS: Mathematical and physical phantoms were used to compare 3D-DFT with Monte Carlo transport (MCT) calculations based on the EGS4 code. The mathematical and physical phantoms consisted of a sphere and a cylinder, respectively, containing uniform and non-uniform activity distributions. Quantitative SPECT reconstruction was carried out using the circular harmonic transform (CHT) algorithm. RESULTS: The radial dose profile obtained from MCT calculations and the 3D-DFT convolution method for the mathematical phantom were in close agreement. The root mean square error (RMSE) for the two methods was < 0.1%, with a maximum difference < 21%. Results obtained for the physical phantom gave a RMSE < 0.1% and a maximum difference of < 13%; isodose contours were in good agreement. SPECT data for two patients who had undergone 131I radioimmunotherapy (RIT) were used to compare absorbed-dose rates and isodose rate contours with the two methods of calculation. This yielded a RMSE < 0.02% and a maximum difference of < 13%. CONCLUSION: Our results showed that the 3D-DFT convolution method compared well with MCT calculations. The 3D-DFT approach is computationally much more efficient and, hence, the method of choice. This method is patient-specific and applicable to the dosimetry of soft-tissue tumors and normal organs. It can be implemented on personal computers.

Absorbed dose calculations in Haversian canals for several beta-emitting radionuclides.

A mathematical model of a Haversian canal was used to calculate absorbed dose factors for 90Sr, 90Y, 45Ca, 89Sr, 32P, 131I and 153Sm. The regions of interest considered in this study were the blood canal, the wall or bone surface and the bone matrix. The source regions were the blood canal and the bone surface. Absorbed dose calculations were performed with the EGS4-PRESTA Monte Carlo transport code. Dose factors were calculated for Haversian canals of 5-microns to 50-microns radius. These data are also tabulated so that dose factors can be evaluated for other radii. An example is given in which these data are used along with a biokinetic model of a radioactive material in bone to assess doses from diagnostic and radiotherapy procedures.

Absorbed dose calculations to blood and blood vessels for internally deposited radionuclides.

At present, absorbed dose calculations for radionuclides in the human circulatory system used relatively simple models and are restricted in their applications. To determine absorbed doses to the blood and to the surface of the blood vessel wall, EGS4 Monte Carlo calculations were performed. Absorbed doses were calculated for the blood and the blood vessel wall (lumen) for different blood vessels sizes. The radionuclides chosen for this study were those commonly used in nuclear medicine. No penetration of the radionuclide into the blood vessel was assumed nor was cross fire between the vessel assumed. The results are useful in assessing the dose to blood and blood vessel walls for different nuclear medicine procedures.