Dosimetry of 188Re-hydroxyethylidene diphosphonate in human prostate cancer skeletal metastases.

188Re-Hydroxyethylidene diphosphonate ((188)Re-HEDP) was used in previous studies for the palliative treatment of metastatic bone pain. However, the kinetic and radiation-absorbed doses have not been well documented. Therefore, the aim of this study was to gather dosimetric data for (188)Re-HEDP. METHODS: Thirteen prostate cancer patients with skeletal involvement were treated with 2,700-3,459 MBq (mean dose, 3,120 MBq) (188)Re-HEDP. Patients underwent whole-body scans 3, 20, and 28 h after therapy. The effective half-life, residence time, and radiation-absorbed dose values were calculated for the whole body, bone marrow, kidneys, and bladder as well as for 29 bone metastases. The urinary excretion rate was determined in 6 urine samples of each patient collected over 48 h at 8-h intervals beginning immediately after the administration of (188)Re-HEDP. After injection of (188)Re-HEDP, blood samples were taken weekly for 6 wk, and platelet and leukocyte counts were performed. RESULTS: The mean effective half-life was 15.9 +/- 3.5 h in bone metastases, 10.9 +/- 2.1 h in the bone marrow, 11.6 +/- 2.1 h in the whole body, 12.7 +/- 2.2 h in the kidneys, and 7.7 +/- 3.4 h in the bladder. The following radiation-absorbed doses were calculated: 3.83 +/- 2.01 mGy/MBq for bone metastases, 0.61 +/- 0.21 mGy/MBq for the bone marrow, 0.07 +/- 0.02 mGy/MBq for the whole body, 0.71 +/- 0.22 mGy/MBq for the kidneys, and 0.99 +/- 0.18 mGy/MBq for the bladder. (188)Re-HEDP showed a rapid urinary excretion within the first 8 h after therapy, with 41% of the (188)Re-HEDP administered being excreted. Forty-eight hours after therapy, the excretion rate was 60% +/- 12%. Only 1 patient showed a decrease of platelet count below 100 x 10(9) counts/L. None of the patients presented with a decrease of leukocyte count below 3.0 x 10(9) counts/L. CONCLUSION: (188)Re-HEDP is an effective radiopharmaceutical used in the palliative treatment of metastatic bone pain. The radiation-absorbed dose is acceptable for bone pain palliation with low doses for the normal bone marrow and the whole body.     

Preparation and evaluation of the rhenium-188-labelled anti-NCA antigen monoclonal antibody BW 250/183 for radioimmunotherapy of leukaemia.

Anti-NCA antigen antibody BW 250/183 (Anti-Granulocyte) localizes more than 50% of injected antibody dose to the bone marrow. Therefore, this antibody is promising for adjuvant conditioning radioimmunotherapy of bone marrow before bone marrow transplantation. To examine its potential use for radioimmunotherapy, we developed an efficient and reproducible technical protocol for labelling anti-NCA antigen antibody BW 250/183 with generator-produced rhenium-188, aiming at both high radiochemical yield and high specific activity. (188)Re-labelled BW 250/183 antibody was used in 12 patients with advanced leukaemia. Labelling of BW 250/183 with (188)Re was accomplished by the direct radiolabelling method using tris-(2-carboxyethyl) phosphine (TCEP) as the reducing agent. Twelve patients with recurrent acute or chronic leukaemia were treated with activities of 6.5-12.4 GBq of (188)Re-labelled BW 250/183. Standard gamma camera scintigraphy was used to evaluate the biodistribution, and a region of interest analysis together with the MIRDOSE 3.1 software was applied to determine the radiation doses to relevant tissues. The (188)Re-BW 250/183 antibody was labelled in high radiochemical yield, with high radiochemical purity (94%+/-3%) and specific activity (5.55-7.4 GBq/mg) within 1 h. The preliminary biodistribution studies showed persistent uptake of (188)Re-BW 250/183 in bone marrow. The radiation absorbed doses (mGy/MBq) delivered to the total body, red marrow, liver, spleen and kidneys were 0.13+/-0.02, 1.45+/-0.71, 0.43+/-0.21, 1.32+/-0.99 and 0.71+/-0. 17, respectively. TCEP reduction enabled the direct, fast and effective labelling of the monoclonal antibody BW 250/183 with (188)Re. Preliminary clinical results suggest delivery of a significant radiation dose to bone marrow and thus the potential for adjuvant conditioning therapy before BMT.     

Biodistribution and radiation dosimetry of [<Superscript>123</Superscript>I]ADAM in healthy human subjects: preliminary results

[(123)I]ADAM [2-((2-((dimethylamino)methyl)phenyl)thio)-5-iodophenylamine (ADAM)] has recently been shown to be a very promising imaging ligand for the detection of serotonin transporters (SERT) in human brain, because of its high specificity for SERT. [(123)I]ADAM has previously been used only for animal studies. In this work, we investigated the radiation dosimetry and biodistribution of [(123)I]ADAM based on whole-body scans in healthy human volunteers. Following the administration of 196+/-20 MBq (range 157-220 MBq) [(123)I]ADAM, serial whole-body images were performed up to 24 h. Estimates of radiation absorbed dose were calculated using the MIRDOSE 3.0 program with a dynamic bladder model. Twelve source organs were considered in estimating absorbed radiation doses for organs of the body. The highest absorbed organ doses were found to the lower large intestine wall (8.3.10(-2) mGy/MBq), kidneys (5.2.10(-2) mGy/MBq), urinary bladder wall (4.9.10(-2) mGy/MBq) and thyroid (4.3.10(-2) mGy/MBq). The effective dose was estimated to be 2.2.10(-2) mSv/MBq. The results suggest that [(123)I]ADAM is of potential value as a tracer for single-photon emission tomography imaging of serotonin receptors in humans, with acceptable dosimetry and high brain uptake.     

Safety, biodistribution, and dosimetry of 123I-IMPY: a novel amyloid plaque-imaging agent for the diagnosis of Alzheimer's disease.

(123)I-IMPY (6-iodo-2-(4'-dimethylamino-)phenyl-imidazo[1,2-a]pyridine) is a novel radiopharmaceutical that selectively binds to Alzheimer's disease (AD) amyloid plaques. As a first step toward validating this radiopharmaceutical as an imaging biomarker for AD, we measured the whole-body biokinetics and radiation dosimetry of (123)I-IMPY in AD patients and cognitively normal control subjects. The pharmacologic safety profile of the compound was simultaneously assessed. METHODS: The sample included 9 subjects ranging in age from 44 to 80 y. Whole-body images were obtained for each subject (mean +/- SD, 9.0 +/- 3.2 scans per subject) for up to 48 h after the intravenous administration of 185 MBq (5 mCi) of (123)I-IMPY. The fraction of administered activity in 12 regions of interest was quantified from the attenuation-corrected geometric mean counts in conjugate views. Multiexponential functions were iteratively fit to each time-activity curve using a nonlinear, least-squares regression algorithm. These curves were numerically integrated to yield cumulated activity values for source organs. Radiation doses were then estimated with the MIRD technique. RESULTS: The radiotracer had no pharmacologic effects (produced no changes in heart rate, blood pressure, or laboratory results) on any of the subjects. Radiation dosimetry estimates indicated that the dose-limiting organ was the gallbladder, which received an average of 0.135 mGy/MBq (range, 0.075-0.198 mGy/MBq). The effective dose equivalent and effective dose for (123)I-IMPY were 0.042 +/- 0.003 mSv/MBq and 0.035 +/- 0.001 mSv/MBq, respectively. The mean effective dose for (123)I-IMPY was similar to that for (111)In-diethylenetriaminepentaacetic acid (0.035 mGy/MBq), less than half that for (111)In-pentetreotide (0.81 mGy/MBq), and approximately twice that for (123)I-IMP (0.018 mGy/MBq). No significant differences were found between men and women or between AD patients and control subjects. CONCLUSION: (123)I-IMPY may be a safe radiotracer with appropriate biokinetics for imaging amyloid plaques in AD patients.     

Radiation dosimetry of a 99mTc-labeled IgM murine antibody to CD15 antigens on human granulocytes.

99mTc-labeled anti-stage specific embryonic antigen-1 (anti-SSEA-1) is an injectable IgM antibody derived from mice. It binds to CD15 antigens on some granulocytic subpopulations of human white blood cells in vivo after systemic administration. The purpose of this study was to measure biodistribution of 99mTc-labeled anti-SSEA-1 and perform radiation dosimetry in 10 healthy human volunteers. METHODS: Transmission scans and whole-body images were acquired sequentially on a dual-head camera for 32 h after the intravenous administration of about 370 MBq (10.0 mCi) of the radiopharmaceutical. Renal excretion fractions were measured from 10 to 14 discrete urine specimens voided over 27.9 +/- 2.0 h. Multiexponential functions were fit iteratively to the time-activity curves for 17 regions of interest using a nonlinear least squares regression algorithm. The curves were integrated numerically to yield source organ residence times. Gender-specific radiation doses were then estimated individually for each subject, using the MIRD technique, before any results were averaged. RESULTS: Quantification showed that the kidneys excreted 39.5% +/- 6.5% of the administered dose during the first 24 h after administration. Image analysis showed that 10%-14% of the radioactivity went to the spleen, while more than 40% went to the liver. Residence times were longest in the liver (3.37 h), followed by the bone marrow (1.09 h), kidneys (0.84 h) and the spleen (0.65 h). The dose-limiting organ in both men and women was the spleen, which received an average of 0.062 mGy/MBq (0.23 rad/mCi, range 0.08-0.30 rad/mCi), followed by the kidneys (0.051 mGy/MBq), liver (0.048 mGy/MBq) and urinary bladder (0.032 mGy/MBq). The effective dose equivalent was 0.018 mSv/MBq (0.068 rem/mCi). CONCLUSION: The findings suggest that the radiation dosimetry profile for this new infection imaging agent is highly favorable.     

In vitro and in vivo evaluation of direct rhenium-188-labeled anti-CD52 monoclonal antibody alemtuzumab for radioimmunotherapy of B-cell chronic lymphocytic leukemia

Alemtuzumab (Campath, Berlex) is a humanized IgG1 rat monoclonal antibody directed against the cell surface CD52 antigen, found on lymphocytes and monocytes. It is being developed for the treatment of chronic lymphocytic leukemia (CLL), autoimmune disease and for the prevention of transplant rejection. This study focused on synthesis, quality control, in vitro evaluation and biodistribution of (188)Re-labeled alemtuzumab for radioimmunotherapy of B-cell CLL. (188)Re-alemtuzumab was synthesized using a direct radiolabeling method. Reduction of the intramolecular disulfide bonds of the antibody was performed with tris-(carboxyethyl)-phosphine (Pierce), using a 1:60 molar excess. Reaction took place at room temperature for 20 min. A PD-10 desalting column was used to purify the reduced antibody from excess phospine. Complexation and transchelation of (188)ReO(4)(-) was achieved using sodium gluconate as weak chelator and SnCl(2) as reducing agent. Quality control was done using instant thin-layer chromatography. Binding assays were performed on a CD52-positive cell line (HuT-78). Female NMRI mice were injected intravenously with 20 microg radiolabeled alemtuzumab and killed at preset time intervals for biodistribution studies. Tissues were dissected, weighed and counted for determination of radioactivity. Data were expressed as percentage injected activity per gram of tissue (% IA/g tissue) or as percentage injected activity (% IA). (188)Re-alemtuzumab was prepared achieving high radiochemical yields. Labeling efficiency of more than 95% can be obtained using optimal reaction conditions. (188)Re-alemtuzumab showed good in vitro stability, remaining intact at 24 h after radiolabeling. In mice, (188)Re-alemtuzumab showed high uptake in the blood (25.10+/-1.36% IA at 1 h p.i.), followed by a biexponential clearance (t(1/2alpha)=4.790 h and t(1/2beta)=55.45 h). Increased uptake was observed in kidneys and heart (9.29+/-0.46% IA/g in kidneys and 6.10+/-1.82% IA/g in heart at 1 p.i.). The highest absorbed radiation dose was received by the kidneys (0.159-3.26 mGy/MBq) and heart wall (0.0705-0.132 mGy/MBq). The predicted radiation dose for the total body was in the range of 0.0459-0.0529 mGy/MBq. The effective dose for the human reference adult was estimated to be approximately 0.0486-0.195 mSv/MBq. (188)Re-alemtuzumab can be prepared with high radiochemical yield and purity and showed good in vitro behavior and favorable biodistribution. Therefore, (188)Re-alemtuzumab would be an ideal candidate for radioimmunotherapy of chronic lymphocytic leukemia.     

Patient-specific dosimetry calculations using mathematic models of different anatomic sizes during therapy with 111In-DTPA-D-Phe1-octreotide infusions after catheterization of the hepatic artery.

The aim of the study was to provide dosimetric data on intrahepatic (111)In-diethylenetriaminepentaacetic acid (DTPA)-D-Phe(1)-octreotide therapy for neuroendocrine tumors with overexpression of somatostatin receptors. METHODS: A dosimetric protocol was designed to estimate the absorbed dose to the tumor and healthy tissue in a course of 48 treatments for 12 patients, who received a mean activity of 5.4 +/- 1.7 GBq per session. The patient-specific dosimetry calculations, based on quantitative biplanar whole-body scintigrams, were performed using a Monte Carlo simulation program for 3 male and 3 female mathematic models of different anatomic sizes. Thirty minutes and 2, 6, 24, and 48 h after the radionuclide infusion, blood-sample data were collected for estimation of the red marrow radiation burden. RESULTS: The mean absorbed doses per administered activity (mGy/MBq) by the critical organs liver, spleen, kidneys, bladder wall, and bone marrow were 0.14 +/- 0.04, 1.4 +/- 0.6, 0.41 +/- 0.08, 0.094 +/- 0.013, and (3.5 +/- 0.8) x 10(-3), respectively; the tumor absorbed dose ranged from 2.2 to 19.6 mGy/MBq, strongly depending on the lesion size and tissue type. CONCLUSION: The results of the present study quantitatively confirm the therapeutic efficacy of transhepatic administration; the tumor-to-healthy-tissue uptake ratio was enhanced, compared with the results after antecubital infusions. Planning of treatment was also optimized by use of the patient-specific dosimetric protocol.     

Biodistribution and radiation dosimetry of [N-methyl-11C]mirtazapine, an antidepressant affecting adrenoceptors.

Central adrenoceptors cannot currently be studied by PET neuroimaging due to a lack of appropriate radioligands. The fast-acting antidepressant drug mirtazapine, radiolabelled for PET, may be of value for assessing central adrenoceptors, provided that the radiation dosimetry of the radioligand is acceptable. To obtain that information, serial whole-body images were made for up to 70 min following intravenous injection of 326 and 185 MBq [N-methyl-11C]mirtazapine (specific activities E.O.S. of 119 and 39G Bq/micromol, respectively) in a healthy volunteer. Ten source organs plus remaining body were considered in estimating absorbed radiation doses calculated using MIRD 3.1. The highest absorbed organ doses were found to the lungs (3.4 x 10(-2) mGy/MBq), adrenals (1.2 x 10(-2) mGy/MBq), spleen (1.2 x 10(-2) mGy/MBq), and gallbladder wall (1.1 x 10(-2) mGy/MBq). The effective dose was estimated to be 6.8 x 10(-3) mSv/MBq, which is similar to that produced by several radioligands used routinely for neuroimaging.     

Biokinetics and dosimetry in patients of 99mTc-EDDA/HYNIC-Tyr3-octreotide prepared from lyophilized kits.

99mTc-EDDA/HYNIC-Tyr3-octreotide (99mTc-HYNIC-TOC) has shown high in vitro and in vivo stability, rapid background clearance and rapid detection of somatostatin receptor-positive tumors. The aim of this study was to establish a biokinetic model for 99mTc-HYNIC-TOC prepared from lyophilized kits, and to evaluate its dosimetry as a tumor imaging agent in patients with histologically confirmed neuroendocrine tumors. Whole-body images from eight patients were acquired at 5, 60, 90, 180 min and 24 h after 99mTc-HYNIC-TOC administration obtained from instant freeze-dried kit formulations with radiochemical purities >95%. Regions of interest (ROIs) were drawn around source organs on each time frame. The same set of ROIs was used for all eight scans and the count per minute (cpm) of each ROI was converted to activity using the conjugate view counting method. The image sequence was used to extrapolate 99mTc-HYNIC-TOC time-activity curves in each organ, to adjust a biokinetic model using the SAAM software, and to calculate the total number of disintegrations (N) that occurred in the source regions. N data were the input for the OLINDA/EXM code to calculate internal radiation dose estimates. Images showed an average tumor/blood (heart) ratio of 4.3+/-0.7 in receptor-positive tumors at 1 h. The mean radiation absorbed dose calculated for a study using 740 MBq was 24, 21.5, 5.5 and 1.0 mSv for spleen, kidneys, liver and bone marrow respectively and the effective dose was 4.4 mSv.     

Intrathecal therapy with 198Au-colloid for meningosis prophylaxis

Telecobalt irradiation in combination with intrathecal (IT) methotrexate has been replaced by IT 198Au-colloid and methotrexate for meningosis prophylaxis in leukemia. Seventy-seven children received 56-200 MBq 198Au-colloid. The distribution was measured with a scintillation camera having a data processing facility. The radiopharmaceutical is adsorbed at the surface of the spaces with cerebrospinal fluid (CSF) 10-20 h after application. The normal retention of the administered radioactivity in the intracranial subarachnoid space (ISS) and in the spinal subarachnoid space (SSS) were 52 +/- 10% and 26 +/- 9%, respectively. An impairment of the normal distribution was observed after IT methotrexate and also postinjection CSF leakage. The calculated radiation absorbed doses in the cerebral and spinal meninges at a depth of 0.01 cm, i.e. the thickness of the pia, were 45 +/- 17 mGy and 189 +/- 91 mGy, respectively, for 1 MBq administered 198Au-colloid. The dosimetry shows that an effective radiation absorbed dose of 18 Gy can be delivered to the cerebral meninges by the application of 400 MBq 198Au-colloid.     

Biodistribution and absorbed radiation dose estimates of 99mTc-labeled dimercaptopropionyl human serum albumin.

The use of 99mTc-labeled red blood cells (RBC) for the evaluation of left ventricular function using equilibrium-gated blood-pool imaging suffers from several problems and potential risks. In this study, we estimated the absorbed radiation dose of 99mTc-labeled dimercaptopropionyl human serum albumin (DMP-HSA) as a potential alternative to 99mTc-RBC. METHODS: After the administration of 99mTc-DMP-HSA, whole-body imaging was performed up to 48 h after injection in five volunteers. The heart contents, liver and remainder of the body were used as source organs. Multicompartment modeling of the biodistribution was performed and absorbed radiation dose estimates for 99mTc-DMP-HSA were obtained using the Medical Internal Radiation Dose (MIRD) calculation. RESULTS: Residence times of 0.62 and 0.43 h were obtained for the heart contents and liver, respectively. Radiation dose estimates yielded an effective dose of 0.0055 mSv/MBq. CONCLUSION: 99MTC-DMP-HSA yielded absorbed radiation doses comparable with those of 99mTc-RBC. Therefore, the radiation properties of 99mTc-DMP-HSA are such that it can be used for clinical diagnostic studies.     

Biodistribution and radiation dosimetry of stabilized 99mTc-exametazine-labeled leukocytes in normal subjects.

Labeling leukocytes with 99mTc-exametazime is a validated technique for imaging infection and inflammation. A new radiolabeling technique has recently been described that enables leukocyte labeling with a more stable form of 99mTc-exametazime. A normal value study of stabilized 99mTc-exametazime-labeled leukocytes has been performed, including biodistribution and dosimetry estimates in normal subjects. METHODS: Ten volunteers were injected with stabilized 99mTc-exametazime-labeled autologous leukocytes to study labeled leukocyte kinetics and dosimetry in normal subjects. Serial whole-body imaging and blood sampling were performed up to 24 h after injection. Cell-labeling efficiency and in vivo viability, organ dosimetry, and clearance calculations were obtained from the blood samples and imaging data as well as urine and stool collection up to 36 h after injection. RESULTS: Cell-labeling efficiency of 87.5% +/- 5.1% was achieved, which is similar to or better than that reported with the standard preparation of 99mTc-exametazime. In vivo stability of the radiolabeled leukocytes was also similar to in vitro results with stabilized 99mTc-exametazime and better than previously reported in vivo stability for nonstabilized 99mTc-exametazime-labeled leukocytes. Organ dosimetry and radiation absorbed doses were similar with a whole-body absorbed dose of 1.3 x 10(-3) mGy/ MBq. Urinary and fecal excretion of activity was minimal, and visual assessment of the images showed little renal parenchymal activity and no bowel activity up to 2 h after injection. CONCLUSION: Cell labeling and in vivo stability appear improved compared with the leukocytes labeled with the nonstabilized preparation of 99mTc-exametazime. There are advantages in more cost-effective preparation of the stabilized 99mTc-exametazime and an extended window for clinical usage, with good visualization of abdominal structures on early images. No significant increase in specific organ and whole-body dosimetry estimates was noted compared with previous estimates using nonstabilized 99mTc-exametazime-labeled leukocytes.     

Patient dosimetry of intravenously administered 99mTc-annexin V.

Annexin V labeled with 99mTc is evaluated as a potential in vivo marker for tissue with increased apoptosis. Promising results in patients have been obtained with 99mTc-(n-1-imino-4-mercaptobutyl)-annexin V (99mTc-i-AnxV). Because information on biodistribution and radiation burden is desired for the application of any radiopharmaceutical, a dosimetric study of 99mTc-i-AnxV was undertaken. METHODS: Eight persons with normal kidney and liver functions were included in this study: six patients with myocardial infarction, one with Crohn's disease, and one healthy volunteer. Approximately 600 MBq 99mTc-i-AnxV were injected intravenously immediately before a dynamic study with a dual-head gamma camera in conjugate view mode. In the next 24 h, two to four whole-body scans were acquired. Patient thickness was determined from a transmission scan with a 57Co flood source. Organ uptake was estimated after correction for background, attenuation, and scatter, using a depth-independent buildup factor and an organ-size-dependent attenuation correction. Residence times were calculated from the dynamic and whole-body studies and used as input for the MIRDOSE 3.1 program to obtain organ-absorbed doses and effective dose. RESULTS: Activity strongly accumulated in the kidneys (21% +/- 6% of the injected dose at 4 h postinjection) and the liver (12.8% +/- 2.2%). Uptake in the target tissues (myocardium or colon) was limited and negligible from a dosimetric point of view. The biologic half-life of activity registered over the total body was 62 +/- 13 h. Of the excreted activity, approximately 75% went to the urine and 25% to the feces. The absorbed dose for the more strongly exposed organs was (in microGy/MBq): kidneys, 93 +/- 24; spleen, 22 +/- 6; liver, 17 +/- 2; testes, 15 +/- 3; thyroid, 10 +/- 6; urinary bladder wall, 7.5 +/- 2.6; and red bone marrow, 5.5 +/- 0.8. The effective dose was 9.7 +/- 1.0 microSv/MBq, corresponding to a total effective dose of 5.8 +/- 0.6 mSv for a nominally injected activity of 600 MBq. CONCLUSION: 99mTc-i-AnxV strongly accumulates in the kidneys and to a lesser degree in the liver. The associated effective dose per MBq is in the midrange of values found for routine 99mTc-labeled compounds. From a dosimetric point of view 99mTc-i-AnxV is therefore well suited for the study of apoptosis in patients.     

Dose estimation in strontium-89 radiotherapy of metastatic prostatic carcinoma.

Strontium-89 radiotherapy is becoming an important treatment in the palliation of bone pain from osteoblastic metastases. The absorbed dose delivered to bone metastases during 89Sr radiotherapy has been estimated in four patients with metastatic prostatic carcinoma. Patients were injected with a tracer dose of 85Sr-chloride. Blood and urine samples were obtained during the week following injection. Strontium-85 scintigrams of metastases and normal bone were obtained up to 8 wk postinjection. Half of the patients showed elevated whole-body retention; plasma-strontium concentrations were decreased from normal values. Uptake of strontium in metastases was 2-25 times that in normal bone but rates of washout of strontium from metastases were similar to those from normal bone. Absorbed doses delivered in infinite time to the metastases by 89Sr ranged from 21 +/- 4 to 231 +/- 56 cGy/MBq with a median value of 68 cGy/MBq. Doses to red marrow were less by a factor of 2 to 50. These absorbed doses are sufficiently large to be expected to produce a therapeutic benefit.     

Estimation of absorbed doses in humans due to intravenous administration of fluorine-18-fluorodeoxyglucose in PET studies

Radiation absorbed doses due to intravenous administration of fluorine-18-fluorodeoxyglucose in positron emission tomography (PET) studies were estimated in normal volunteers. The time-activity curves were obtained for seven human organs (brain, heart, kidney, liver, lung, pancreas, and spleen) by using dynamic PET scans and for bladder content by using a single detector. These time-activity curves were used for the calculation of the cumulative activity in these organs. Absorbed doses were calculated by the MIRD method using the absorbed dose per unit of cumulated activity, "S" value, transformed for the Japanese physique and the organ masses of the Japanese reference man. The bladder wall and the heart were the organs receiving higher doses of 1.2 x 10(-1) and 4.5 x 10(-2) mGy/MBq, respectively. The brain received a dose of 2.9 x 10(-2) mGy/MBq, and other organs received doses between 1.0 x 10(-2) and 3.0 x 10(-2) mGy/MBq. The effective dose equivalent was estimated to be 2.4 x 10(-2) mSv/MBq. These results were comparable to values of absorbed doses reported by other authors on the radiation dosimetry of this radiopharmaceutical.     

Myelotoxicity and RBE of 211At-conjugated monoclonal antibodies compared with 99mTc-conjugated monoclonal antibodies and 60Co irradiation in nude mice.

The rationale of this study was to determine the myelotoxicity in nude mice of the alpha-emitter 211At conjugated to monoclonal antibodies (mAbs) and to compare the effect with an electron emitter, (99m)Tc, and external irradiation from a 60Co source, for estimation of the relative biological effectiveness (RBE). METHODS: 211At and (99m)Tc were conjugated to the IgG1 mAbs MX35 and 88BV59. Nude female BALB/c mice, 8- to 12-wk old, were injected intraperitoneally or intravenously. The biodistribution was determined 3, 6, and 18 h after injection. The bone-to-blood and bone marrow-to-blood activity concentration ratios (BBLR and BMBLR, respectively) were determined for simultaneously injected 211At- and (99m)Tc-mAbs. Bone marrow samples were taken from the femur. For each mouse, the whole-body retention was measured as well as the blood activity by repeated blood samples from the tail vein (0), 1, 3, 6, 12, and 18 h after injection. External-beam irradiation from a 60Co source was also performed at 3 different dose levels. White blood cell (WBC) counts, red blood cell counts, platelet counts, and hemoglobin were determined for each mouse initially and on days 1, 4, 5, 7, 15, 22, and 27 after injection. The calculations of the absorbed dose to the bone marrow were based on the BBLR, BMBLR, the cumulated activities, and the absorbed fractions. The absorbed fractions, phi, for alpha-particles and electrons in the bone marrow were calculated using Monte Carlo simulations based on a bone marrow dosimetry model. RESULTS: The BMBLR was 0.58 +/- 0.06 and 0.56 +/- 0.06 for the 211At- and (99m)Tc-mAbs, respectively. No significant variation in BMBLR with time was found. The absorbed fractions for alpha-particles and electrons in the bone marrow were 0.88 and 0.75, respectively. The mean absorbed fractions of the photons from (99m)Tc were 0.033 and 0.52 for 140 and 18.3 keV, respectively. When different amounts of 211At- and (99m)Tc-mAbs (0.09-1.3 and 250-1,300 MBq, respectively) were administered intraperitoneally or intravenously, corresponding to absorbed doses to the bone marrow of 0.01-0.60 and 0.39-1.92 Gy, respectively, the WBC counts was suppressed by 1%-90% and 23%-89%, respectively. When external-beam irradiation with a 60Co source was performed to absorbed doses of 1.4, 1.9, and 2.4 Gy, the WBC counts was suppressed by 47%-90%. These results indicate a myelotoxic in vivo RBE of 3.4 +/- 0.6 for alpha-particles compared with (99m)Tc and 5.0 +/- 0.9 compared with 60Co irradiation. CONCLUSION: The effect on the WBC counts from bone marrow irradiation with 211At-mAbs indicates an in vivo RBE of 3.4 +/- 0.6 in comparison with (99m)Tc-mAbs. The RBE value compared with external irradiation is 5.0 +/- 0.9.     

Dosimetry of iodine-123 iomazenil in humans

The distribution of the central benzodiazepine receptor specific ligand iodine-123 iomazenil was investigated in seven human adults from whole-body scans, blood samples and urine collected up to 24 h after injection. Using 12 source organs, the MIRD method was applied to calculate the absorbed radiation dose of the radioligand in various organs. The urinary bladder wall (0.15 mGy/MBq), lower large intestinal wall (0.071 mGy/MBq) testes (0.044 mGy/MBq) and upper large intestined wall (0.038 mGy/MBq) received the highest absorbed doses. The average effective dose equivalent of ¹²³I-IBZM for adults was estimated to be 0.033 mSv/MBq.     

Monoclonal antibody BW431/26 labelled with technetium 99m and indium 111: an investigation of the biodistribution and the dosimetry in patients.

As a competitive diagnostic tool for the detection of malignant tumours and other pathological conditions, monoclonal antibodies have long been established. Herein we give the biokinetic data of the antibody BW 431/26 and the consequent radiation dose to patients. These parameters were recorded in 39 patients, using the antibody labelled either with technetium 99m or indium 111. Remarkable differences were observed between the two radionuclides. Whereas the indium-labelled one showed biexponential elimination kinetics, the technetium-labelled one is eliminated linearly over time. The distribution pattern of the two is identical, although the radiation dose varies quite a lot, being 20-fold higher with indium 111 when total body exposure is taken into account (for 111In the whole-body radiation exposure is 0.1 mGy/MBq; for 99mTc it is 0.0047 mGy/MBq). With respect to these results and considering the general availability of the technetium-labelled Ab, it is the best choice for diagnostic use.     

Radiation doses of yttrium-90 citrate and yttrium-90 EDTMP as determined via analogous yttrium-86 complexes and positron emission tomography

Yttrium-90 is used for palliative therapy for the treatment of skeletal metastases, but because it is a pure - emitter, data on the pharmacokinetics and radiation doses to metastases and unaffected organs are lacking. To obtain such data, the present study employed yttrium-86 as a substitute for⁹⁰Y, with detection by positron emission tomography (PET). The study compared the properties of two different⁸⁶Y complexes —⁸⁶y-citrate and⁸⁶Y -ethylene diamine tetramethylene phosphonate (EDTMP) — in ten patients with prostatic cancer who had developed multiple bone metastases (the ten patients being divided into two groups of five). Early dynamics were measured up to 1 h post injection (p.i.) over the liver region, followed by subsequent whole-body PET scans up to 3 days p.i. Absolute uptake data were determined for normal bone, bone metastases, liver and kidney. Radiation doses were calculated according to the MIRD recommendations. Based on the pharmacokinetic measurements of the distribution of the⁸⁶Y complexes, it was possible to calculate radiation doses for the bone metastases and the red bone marrow delivered by complexes containing⁹⁰Y. In 1 cm³ of bone metastasis, doses of 26±11 mGy/MBq and 18±2 mGy/MBq were determined per MBq of injected⁹⁰Y- citrate and⁹⁰Y- EDTMP, respectively. The doses to the bone marrow were 2.5±0.4 mGy/MBq for⁹⁰Y- citrate and 1.8±0.6 mGy/MBq for⁹⁰Y-EDTMP.⁸⁶Y and PET provide quantitative information applicable to the clinical use of⁹⁰Y. This method may also be useful for the design of other⁹⁰Y radiopharmaceuticals and for planning radiotherapy dosages.     

Dosimetric analysis of radioimmunotherapy with 186Re-labeled bivatuzumab in patients with head and neck cancer.

From December 1999 until July 2001, a phase I dose escalation study was performed with (186)Re-labeled bivatuzumab, a humanized monoclonal antibody against CD44v6, on patients with inoperable recurrent or metastatic head and neck cancer. The aim of the trial was to assess the safety and tolerability of intravenously administered (186)Re-bivatuzumab and to determine the maximum tolerated dose (MTD) of (186)Re-bivatuzumab. The data were also used for dosimetric analysis of the treated patients. Dosimetry is used to estimate the absorbed doses by nontarget organs, as well as by tumors. It can also help to explain toxicity that is observed and to predict organs at risk because of the therapy given. METHODS: Whole-body scintigraphy was used to draw regions around sites or organs of interest. Residence times in these organs and sites were calculated and entered into the MIRDOSE3 program, to obtain absorbed doses in all target organs except for red marrow. The red marrow dose was calculated using a blood-derived method. Twenty-one studies on 18 patients, 5 female and 16 male, were used for dosimetry. RESULTS: The mean red marrow doses were 0.49 +/- 0.03 mGy/MBq for men and 0.64 +/- 0.03 mGy/MBq for women. The normal organ with the highest absorbed dose appeared to be the kidney (mean dose, 1.61 +/- 0.75 mGy/MBq in men and 2.15 +/- 0.95 mGy/MBq in women; maximum kidney dose in all patients, 11 Gy), but the doses absorbed are not expected to lead to renal toxicity. Other organs with doses exceeding 0.5 mGy/MBq were the lungs, the spleen, the heart, the liver, the bones, and the testes. The doses delivered to the tumor, recalculated to the MTD level of 1.85 GBq/m(2), ranged from 3.8 to 76.4 Gy, with a median of 12.4 Gy. A good correlation was found between platelet and white blood cell counts and the administered amount of activity per kilogram of body weight (r = -0.79). CONCLUSION: Dosimetric analysis of the data revealed that the range of doses to normal organs seems to be well within acceptable and safe limits. Tumor doses ranged from 4 to 76 Gy. Given the acceptable tumor doses, (186)Re-labeled bivatuzumab could be a good candidate for future adjuvant radioimmunotherapy in patients with minimal residual disease.