Phase I/II clinical trial of the humanized anti-EGF-r monoclonal antibody h-R3 labelled with 99mTc in patients with tumour of epithelial origin

AIM: To evaluate the biodistribution, internal radiation dosimetry and toxicity of the humanized MAb h-R3 labelled with Tc in humans. METHODS: Twenty-five patients with suspected epithelial-derived tumours were included in this study and divided into two groups: group I consisted of 10 patients who received 3 mg/1110 MBq (3 mg/30 mCi); and group II consisted of 15 patients who received 6 mg/2220 MBq (6 mg/60 mCi). Single photon emission computed tomography (SPECT) and planar images, and multiple blood and urine samples were collected up to 24 h after injection. Haematological parameters and adverse effects were classified according to the WHO criteria. Biodistribution, human anti-mouse antibody (HAMA) response and absorbed doses were estimated and reported. RESULTS: Liver, spleen, kidneys and heart were identified as source organs. Their higher uptakes were 53.3+/-6.4%ID, 2.0+/-1.4%ID, 9.8+/-4.3%ID and 2.8+/-0.9%ID, respectively. The urinary bladder and large intestine also had a significant uptake. The mean urinary excretion was around 22%ID. The liver received the highest absorbed doses followed by the kidneys and the urinary bladder wall. There were no haematological or biochemical abnormalities with clinical significance related to the product. No patient developed HAMA response. Preliminary analysis of clinical results showed a sensitivity of 76.5% and a specificity of 100%. CONCLUSIONS: The results of this study suggest that Tc-h-R3 could be used in patients in a safe and effective way, for the diagnosis of epithelial-derived tumours at the two evaluated dose levels.     

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.     

Radioimmunotherapy for the intensification of conditioning before stem cell transplantation: differences in dosimetry and biokinetics of 188Re- and 99mTc-labeled anti-NCA-95 MAbs.

A new concept is the intensification of preparative regimens for patients with advanced leukemia using monoclonal antibodies (MAbs) with an affinity for beta emitter-labeled bone marrow. 188Re is a high-energy beta emitter that has therapeutic promise. Our first aim was to clarify whether the therapeutic application of 188Re-MAb against nonspecific cross-reacting antigen 95 (NCA-95) can be predicted from biokinetic data derived from 99mTc-labeled NCA-95. Our second aim was to show that a radiation absorbed dose of > or =12 Gy in the bone marrow can be achieved using 188Re-MAb. METHODS: Dosimetric data were obtained for both radiotracers from multiple planar whole-body scans (double-head gamma camera), blood samples, and urine measurements from 12 patients with advanced leukemia. Radiation absorbed doses were calculated using MIRDOSE 3 software. RESULTS: Radiation absorbed doses to bone marrow, liver, spleen, lung, and kidney were 2.24, 0.50, 1.93, 0.05, and 0.90 mGy/MBq, respectively, using 99mTc-MAb and 1.45, 0.43, 1.32, 0.07, and 0.71 mGy/MBq, respectively, using 188Re-MAb. These differences were statistically significant for bone marrow, spleen, and kidney. The main differences were less accumulation of 188Re-MAb in bone marrow (31%+/-13% compared with 52%+/-13%) and faster elimination through urine (25%+/-3% compared with 15%+/-5% after 24 h). On the basis of these data, a mean marrow dose of 14+/-7 Gy was achieved in 12 patients suffering from leukemia after application of approximately 10+/-2 GBq 188Re-MAb. CONCLUSION: Myeloablative radiation absorbed doses can easily be achieved using 188Re-MAb. 99mTc- and 188Re-MAb showed similar whole-body distributions. However, direct prediction of radiation absorbed doses from the 99mTc-MAb, assuming identical biokinetic behavior, is not valid for the 188Re-MAb in a single patient. Therefore, individual dosimetry using 188Re-MAb is needed to calculate therapeutic activity.     

Radiolabeling, biodistribution, and dosimetry of (123)I-mAb 14C5: a new mAb for radioimmunodetection of tumor growth and metastasis in vivo.

This study reports on the in vitro evaluation, biodistribution, and dosimetry of (123)I-labeled monoclonal antibody (mAb) 14C5, a new antibody-based agent proposed for radioimmunodetection of tumor growth and metastasis in vivo. METHODS: (123)I-mAb 14C5 was prepared by direct iodination and tested for stability in vitro. Binding assays were performed on human SK-BR-3 and HeLa carcinoma cells to investigate the antigen expression, antibody affinity, and kinetics of tracer binding. For the biodistribution and dosimetry study, 3- to 4-wk-old NMRI mice were injected intravenously with (123)I-mAb 14C5 (148.0 +/- 7.4 kBq per mouse) and killed at preset time intervals. Organs, blood, urine, and feces were counted for radioactivity uptake, and the data were expressed as the percentage injected dose per gram tissue (%ID/g tissue) or %ID. The MIRDOSE3.0 program was applied to extrapolate the estimated absorbed radiation doses for various organs to the human reference adult. RESULTS: (123)I-mAb 14C5 was obtained in radiochemical yields of 85.0% +/- 2.5% and radiochemical purities were >97%. The iodinated antibody demonstrated good in vitro stability with 93.6% +/- 0.1% of (123)I-mAb 14C5 remaining intact at 24 h after radiolabeling. (123)I-mAb 14C5 bound to SK-BR-3 cells (dissociation constant [K(d)] approximately 0.85 +/- 0.17 nmol/L) and HeLa cells (K(d) approximately 1.71 +/- 0.17 nmol/L) with nanomolar affinity and high specificity, whereas both cell types exhibited a high CA14C5 antigen expression (maximum number of binding sites [B(max)] = 40.6 +/- 5.2 and 57.1 +/- 9.6 pmol/L, respectively). In mice, (123)I-mAb 14C5 accumulated primarily in lungs (20.4 %ID/g), liver (15.1 %ID/g), and kidneys (11.1 %ID/g) within 5 min after injection. A delayed uptake was observed in stomach (12.8 %ID/g) and urinary bladder (8.7 %ID/g) at 3 and 6 h, respectively, after injection. Radioactivity clearance was predominantly urinary, with 44.9 +/- 4.5 %ID excreted during the initial 48 h after administration (cumulative amount). The highest absorbed radiation doses determined for the human reference adult were received by the urinary bladder wall (0.1200-0.1210 mGy/MBq), liver (0.0137-0.0274 mGy/MBq), uterus (0.0196-0.0207 mGy/MBq), and lower large intestine wall (0.0139-0.0258 mGy/MBq). The average effective dose resulting from a single (123)I-mAb 14C5 injection was estimated to be 0.017-0.022 mSv/MBq. CONCLUSION: (123)I-mAb 14C5 shows good in vitro biologic activity and favorable biodistribution properties for imaging carcinomas of different origin and provides an acceptable radiation dose to the patient.     

Radiation dosimetry estimates of [18F]-fluoroacetate based on biodistribution data of rats

We estimated the dosimetry of [(18)F]fluoroacetate (FAC) with the method established by MIRD based on biodistribution data of rats. We selected some important organs and computed their residence time, their absorbed doses and effective dose with the (%ID(Organ)) (human) data using OLINDA/EXM 1.1 program. We observed the highest absorbed doses in the heart wall (0.025mGy/MBq) and the lowest in skin (0.0079mGy/MBq). The total mean absorbed doses and the effective doses were 0.011mGy/MBq and 0.014mSv/MBq, respectively. A 370-MBq injection of FAC leads to an estimated effective dose of 5.2mSv. The potential radiation risk associated with FAC/PET imaging is well within the accepted limits.     

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.     

Safety, biodistribution, and dosimetry of 99mTc-HYNIC-annexin V, a novel human recombinant annexin V for human application.

99mTc-hydrazinonicotinamido (HYNIC)-annexin V is a novel tracer for in vivo imaging of apoptosis. The present study on humans was performed to investigate the safety of (99m)Tc-HYNIC-annexin V and to quantify the biodistribution and radiation dose. METHODS: Six healthy, male volunteers participated in the study. A dual-head gamma camera was used to acquire conjugate anterior and posterior views. Imaging started with a transmission scan using a (57)Co-flood source to obtain a map of the local thickness of the volunteer. Approximately 250 MBq of (99m)Tc-HYNIC-annexin V were injected intravenously, directly followed by a 30-min dynamic study. Whole-body scans were obtained at about 30 min, 3 h, 6 h, and 24 h after injection. Organ uptake was determined after correction for background, scatter, and attenuation. The MIRDOSE3.1 program was used to calculate organ-absorbed doses and effective dose. Signs of adverse effects were investigated by monitoring renal and liver function, hematology, blood coagulation, and vital signs (blood pressure, pulse, respiration rate, temperature, and electrocardiogram). RESULTS: The kidneys accumulated 49.7 +/- 8.1 percentage injected dose (%ID) at 3 h after injection; the liver, 13.1 +/- 1.0 %ID; the red marrow, 9.2 +/- 1.8 %ID; and the spleen, 4.6 +/- 1.6 %ID. More than 90% of the blood activity was cleared with a half-life of 24 +/- 3 min. The biologic half-life of the activity registered over the total body was long (69 +/- 7 h). Excretion of the activity was almost exclusively through the urine (22.5 +/- 3.5 %ID at 24 h), and hardly any activity was seen in the bowel or feces. Absorbed doses were found to be 196 +/- 31 micro Gy/MBq for the kidneys, 41 +/- 12 micro Gy/MBq for the spleen, 16.9 +/- 1.3 micro Gy/MBq for the liver, and 8.4 +/- 0.9 micro Gy/MBq for the red marrow. The effective dose was 11.0 +/- 0.8 micro Sv/MBq, or 2.8 +/- 0.2 mSv for the average injected activity of 250 MBq. No adverse effects were observed. CONCLUSION: (99m)Tc-HYNIC-annexin V is a safe radiopharmaceutical, having a favorable biodistribution for imaging of apoptosis in the abdominal as well as thoracic area with an acceptable radiation dose.     

Biodistribution and radiation dosimetry of the dopamine D2 ligand 11C-raclopride determined from human whole-body PET.

Whole-body radiation dosimetry of 11C-raclopride was performed in healthy human volunteers. METHODS: Subjects (n = 6) were scanned with PET. Subjects received single-bolus injections of 11C-raclopride (S-(-)-3,5-dichloro-N-[(1-ethyl-2-pyrrolidinyl)]methyl-2-hydroxy-6-methoxybenzamide) (533 +/- 104 MBq) and were scanned for approximately 110 min with a 2-dimensional whole-body protocol. Regions of interest were placed over all visually identifiable organs and time-activity curves were generated. Residence times were computed as the area under the curve of the time-activity curves, normalized to injected activities and standard values of organ volumes. Absorbed doses were computed according to the MIRD schema with MIRDOSE3.1 software. RESULTS: Organs with the highest radiation burden were gallbladder wall, small intestine, liver, and urinary bladder wall. CONCLUSION: On the basis of the estimated absorbed dose, the maximum allowable single study dose under U.S. federal regulations for studies performed under Radiation Drug Research Committee is 1.58 GBq (42.8 mCi). This is still considerably higher than the doses of 11C-raclopride commonly used in research PET (370-555 MBq).     

Phase I/II 90Y-Zevalin (yttrium-90 ibritumomab tiuxetan, IDEC-Y2B8) radioimmunotherapy dosimetry results in relapsed or refractory non-Hodgkin's lymphoma

Dosimetry studies in patients with non-Hodgkin's lymphoma were performed to estimate the radiation absorbed dose to normal organs and bone marrow from 90Y-Zevalin (yttrium-90 ibritumomab tiuxetan, IDEC-Y2B8) treatment in this phase I/II, multicenter trial. The trial was designed to determine the dose of Rituximab (chimeric anti-CD20, Rituxan, IDEC-C2B8, MabThera), the unlabeled antibody given prior to the radioconjugate to clear peripheral blood B cells and optimize distribution, and to determine the maximum tolerated dose of 90Y-Zevalin [7.4, 11, or 15 MBq/kg (0.2, 0.3, or 0.4 mCi/kg)]. Patients received (111)In-Zevalin (indium-111 ibritumomab tiuxetan, IDEC-In2B8 ) on day 0 followed by a therapeutic dose of 90Y-Zevalin on day 7. Both doses were preceded by an infusion of the chimeric, unlabeled antibody Rituximab. Following administration of (111)In-Zevalin, serial anterior/posterior whole-body scans were acquired. Major-organ radioactivity versus time estimates were calculated using regions of interest. Residence times were computed and entered into the MIRDOSE3 computer software program to calculate estimated radiation absorbed dose to each organ. Initial analyses of estimated radiation absorbed dose were completed at the clinical site. An additional, centralized dosimetry analysis was performed subsequently to provide a consistent analysis of data collected from the seven clinical sites. In all patients with dosimetry data (n=56), normal organ and red marrow radiation absorbed doses were estimated to be well under the protocol-defined upper limit of 20 Gy and 3 Gy, respectively. Median estimated radiation absorbed dose was 3.4 Gy to liver (range 1.2-7.8 Gy), 2.6 Gy to lungs (range 0.72-4.4 Gy), and 0.38 Gy to kidneys (range 0.07-0.61 Gy). Median estimated tumor radiation absorbed dose was 17 Gy (range 5.8-67 Gy). No correlation was noted between hematologic toxicity and the following variables: red marrow radiation absorbed dose, blood T(1/2), blood AUC, plasma T(1/2), and plasma AUC. It is concluded that 90Y-Zevalin administered at nonmyeloablative maximum tolerated doses results in acceptable radiation absorbed doses to normal organs. The only toxicity of note is hematologic and is not correlated to red marrow radiation absorbed dose estimates or T(1/2), reflecting that hematologic toxicity is dependent on bone marrow reserve in this heavily pretreated population.     

Dosimetric model for locoregional treatments of brain tumors with 90Y-conjugates: clinical application with 90Y-DOTATOC.

Locoregional (LR) administration of (90)Y-conjugates after surgical debulking is a promising therapeutic option of gliomas. Dosimetry is highly recommended, as patient-specific parameters influence the absorbed dose to target and normal tissues. After tumor resection, the absorbed dose must be carefully evaluated in the rim of tissue surrounding the resected area. The aim of this study was to calculate and provide the S values, according to the MIRD concept, for dosimetry of LR brain treatments with several (90)Y-labeled compounds. The S values thus obtained have been clinically applied in 12 patients treated with (90)Y-labeled [DOTA(0),D-Phe(1),Tyr(3)]octreotide ((90)Y-DOTATOC). METHODS: An anthropomorphic model for Monte Carlo simulations was developed to evaluate absorbed doses in brain-adjacent tissue (BAT) and in normal brain. To adapt the model to single patients, S values were evaluated taking into account (i) different surgical resection cavity (SRC) volumes, (ii) different percentages of conjugate binding to the cavity wall, and (iii) different depths of percolation of the conjugate trough the cavity wall. BAT was divided into 1-mm-thick consecutive adjacent shells to evaluate the dose distribution around the cavity. Corresponding S values were obtained to allow dosimetric evaluation in brain LR therapy with (90)Y-conjugates. In the clinical treatments, 0.4-1.1 GBq of (90)Y-DOTATOC were injected into the SRC via an appropriate catheter. The activity in the SRC was assumed to be the difference between the total injected activity and the activity in the blood plus the activity cumulatively eliminated with the urine. RESULTS: Assuming no diffusion, with a mean residence time in SRC of 60 +/- 8 h, absorbed doses to shell II were 0.25 and 0.03 Gy/MBq for SRC volumes of 7.2 and 65.4 mL, respectively. Assuming a slight diffusion of 1 mm with a 7.2-mL SRC, absorbed dose to shells I, II, and VI were consistently different: 5.32, 2.53, and 0.12 Gy/MBq, respectively. Mean doses to normal brain, red marrow, bladder wall, and total body were 0.015, 0.03, 1.22, and 0.006 MGy/MBq. CONCLUSION: The model proved to be suitable for the dosimetry of several LR therapies with (90)Y-conjugates. According to our results, LR treatment with (90)Y-DOTATOC can safely deliver very high doses to target tissue, sparing normal organs including brain.     

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. ¹⁸⁸Re-labelled BW 250/183 antibody was used in 12 patients with advanced leukaemia. Labelling of BW 250/183 with ¹⁸⁸Re 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 ¹⁸⁸Re-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 ¹⁸⁸Re-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 ¹⁸⁸Re-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 ¹⁸⁸Re. Preliminary clinical results suggest delivery of a significant radiation dose to bone marrow and thus the potential for adjuvant conditioning therapy before BMT. Received 6 January and in revised form 10 May 1999     

Preclinical pharmacokinetic, biodistribution, toxicology, and dosimetry studies of 111In-DTPA-human epidermal growth factor: an auger electron-emitting radiotherapeutic agent for epidermal growth factor receptor-positive breast cancer.

Our objective was to evaluate the pharmacokinetics, normal tissue distribution, radiation dosimetry, and toxicology of human epidermal growth factor (hEGF) labeled with (111)In ((111)In-diethylenetriaminepentaacetic acid [DTPA]-hEGF) in mice and rabbits. METHODS: (111)In-DTPA-hEGF (3.6 MBq; 1.3 or 13 microg) was administered intravenously to BALB/c mice. The blood concentration-time data were fitted to a 3-compartment model. Acute toxicity was studied with female BALB/c mice at 42 times the maximum planned human dose (MBq/kg) or with New Zealand White rabbits at 1 times the maximum planned human dose (MBq/kg) for a phase I clinical trial. Toxicity was evaluated by monitoring body weight, by determination of hematology and clinical biochemistry parameters, and by morphologic examination of tissues. Radiation dosimetry projections in humans were estimated on the basis of the residence times in mice by use of the OLINDA version 1.0 computer program. RESULTS: The largest amounts of radioactivity were taken up by the liver (41.3 +/- 7.8 [mean +/- SD] percentage injected dose [%ID] at 1 h after injection and decreasing to 4.9 +/- 0.3 %ID at 72 h after injection) and kidneys (18.6 +/- 0.8 %ID at 1 h and decreasing to 4.5 +/- 0.2 %ID at 72 h after injection). (111)In-DTPA-hEGF was cleared rapidly from the blood, with a half-life at alpha-phase of 2.7-6.2 min and a half-life at beta-phase of 24.0-36.3 min. The half-life of the long terminal phase could not be accurately determined. The volume of distribution of the central compartment was 340-375 mL/kg, and the volume of distribution at steady state was 430-685 mL/kg. There was no significant difference in the ratio of body weight at 15 d to pretreatment weight for mice administered (111)In-DTPA-hEGF (1.02 +/- 0.01) and mice administered unlabeled DTPA-hEGF (1.01 +/- 0.01). Erythrocyte, leukocyte, and platelet counts and serum alanine aminotransferase and creatinine levels remained in the normal ranges. No morphologic changes were observed by light microscopy in any of 19 tissues sampled. Minor morphologic changes in the liver were observed by electron microscopy. The projected whole-body dose in humans was 0.19 mSv.MBq(-1). The projected doses to the liver, kidneys, and lower large intestine were 0.76, 1.82, and 1.12 mSv.MBq(-1), respectively. CONCLUSION: (111)In-DTPA-hEGF was safely administered to mice and rabbits at multiples of the maximum dose planned for a phase I trial in breast cancer patients.     

Radiation dosimetry results and safety correlations from 90Y-ibritumomab tiuxetan radioimmunotherapy for relapsed or refractory non-Hodgkin's lymphoma: combined data from 4 clinical trials.

Ibritumomab tiuxetan is an anti-CD20 murine IgG1 kappa monoclonal antibody (ibritumomab) conjugated to the linker-chelator tiuxetan, which securely chelates (111)In for imaging or dosimetry and (90)Y for radioimmunotherapy (RIT). Dosimetry and pharmacokinetic data from 4 clinical trials of (90)Y-ibritumomab tiuxetan RIT for relapsed or refractory B-cell non-Hodgkin's lymphoma (NHL) were combined and assessed for correlations with toxicity data. METHODS: Data from 179 patients were available for analysis. Common eligibility criteria included <25% bone marrow involvement by NHL, no prior myeloablative therapy, and no prior RIT. The baseline platelet count was required to be > or = 100,000 cells/mm(3) for the reduced (90)Y-ibritumomab tiuxetan administered dose (7.4-11 MBq/kg [0.2-0.3 mCi/kg]) or > or = 150,000 cells/mm(3) for the standard (90)Y-ibritumomab tiuxetan administered dose (15 MBq/kg [0.4 mCi/kg]). Patients were given a tracer administered dose of 185 MBq (5 mCi) (111)In-ibritumomab tiuxetan on day 0, evaluated with dosimetry, and then a therapeutic administered dose of 7.4-15 MBq/kg (0.2-0.4 mCi/kg) (90)Y-ibritumomab tiuxetan on day 7. Both ibritumomab tiuxetan administered doses were preceded by an infusion of 250 mg/m(2) rituximab to clear peripheral B-cells and improve ibritumomab tiuxetan biodistribution. Residence times for (90)Y in blood and major organs were estimated from (111)In biodistribution, and the MIRDOSE3 computer software program was used, with modifications to account for patient-specific organ masses, to calculate radiation absorbed doses to organs and red marrow. RESULTS: Median radiation absorbed doses for (90)Y were 7.42 Gy to spleen, 4.50 Gy to liver, 2.11 Gy to lung, 0.23 Gy to kidney, 0.62 Gy (blood-derived method) and 0.97 Gy (sacral image-derived method) to red marrow, and 0.57 Gy to total body. The median effective blood half-life was 27 h, and the area under the curve (AUC) was 25 h. No patient failed to meet protocol-defined dosimetry safety criteria and all patients were eligible for treatment. Observed toxicity was primarily hematologic, transient, and reversible. Hematologic toxicity did not correlate with estimates of red marrow radiation absorbed dose, total-body radiation absorbed dose, blood effective half-life, or blood AUC. CONCLUSION: Relapsed or refractory NHL in patients with adequate bone marrow reserve and <25% bone marrow involvement by NHL can be treated safely with (90)Y-ibritumomab tiuxetan RIT on the basis of a fixed, weight-adjusted dosing schedule. Dosimetry and pharmacokinetic results do not correlate with toxicity.     

Dosimetry of rhenium-188 diethylene triamine penta-acetic acid for endovascular intra-balloon brachytherapy after coronary angioplasty

To examine the possibility of using rhenium-188 diethylene triamine penta-acetic acid (DTPA) for endovascular intra-balloon brachytherapy after angioplasty, dose distribution around the balloon was calculated and validated by film dosimetry. Medical internal radiation dosimetry (MIRD) was calculated assuming that the balloon had ruptured and that the contents had been released into the systemic circulation. 188Re-perrhenate eluate from the 188W/188Re generator was concentrated using an ion column and used to label DTPA. The dose distribution around the angioplasty balloon (20 mm length, 3 mm diameter cylinder) was estimated by Monte Carlo simulation using the EGS4 code. The time required for 17.6 Gy to be absorbed at 1 mm from the balloon's surface following application of 3700 MBq/ml of 188Re was found to be 278 s. Fifty percent of the energy was deposited in the first millimetre of the vessel wall from the balloon's surface. The calculated radiation absorbed dose agreed with that measured by film dosimetry, which was performed using a water phantom, with errors ranging from 9.4% to 17%. Upon balloon rupture the total amount of 188Re-DTPA was presumed to enter the systemic circulation. The resulting radiation absorbed dose was calculated using the MIRDOSE3 program and residence times obtained from dogs and amounted to 0.0056 mGy/MBq to the whole body and 4.56 mGy/MBq to the urinary bladder. The absorbed dose of 188Re-DTPA to the whole body was one-tenth of that of 188Re-perrhenate. A window-based program was developed to calculate the exposure time and the radiation dose absorbed as a function of the 188Re concentration and the arbitrary distance from the balloon to the surrounding tissues. We conclude that 188Re-DTPA is easy to prepare, safe to use and suitable for intra-balloon brachytherapy after coronary angioplasty.     

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

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.     

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.     

Pharmacokinetics, dosimetry and comparative efficacy of 188Re-liposome and 5-FU in a CT26-luc lung-metastatic mice model

The biodistribution, pharmacokinetics, dosimetry and comparative therapeutic efficacy of intravenously administrated (188)Re-N,N-bis(2-mercaptoethyl)-N',N'-diethylethylenediamine (BMEDA)-labeled pegylated liposome ((188)Re-liposome) and 5-FU were investigated in a CT26-luc lung-metastatic model. After intravenous administration of (188)Re-liposome, tumor accumulation from the radioactivity was observed. Levels of radioactivity in tumors were maintained at steady levels (from 5.40 to 5.67 %ID/g) after 4 to 24 h. In pharmacokinetics, the AUC((0→∞)), MRT((0→∞)) and Cl of (188)Re-liposome in blood via intravenous route were 998 h %ID/ml, 28.7 h and 0.1 ml/h, respectively. The total excreted fractions of feces and urine were 0.61 and 0.26, respectively. Absorbed doses for (188)Re-liposome in the liver and red marrow were 0.31 and 0.08 mSv/MBq, respectively. Tumor-absorbed doses for (188)Re-liposome ranged from 48.4 to 1.73 mGy/MBq at 10 to 300 g tumor spheres. In therapeutic efficacy, the survival times of mice after (188)Re-liposome [80% maximum tolerated dose (MTD); 29.6 MBq], 5-FU (80% MTD; 144 mg/kg), liposome or normal saline treatments were evaluated. Consequently, radiotherapeutics of (188)Re-liposome attained a longer lifespan (increase of 34.9%; P=.005) in mice than in the normal saline group. The increase in lifespan of the (188)Re-liposome group was 2.5-fold greater than that of the 5-FU group. Therefore, intravenous administration of (188)Re-liposome could provide a benefit and it is a promising strategy for delivery of passive nanotargeted radiotherapeutics in oncology applications.     

Intratumoral injection with [(188)Re]rhenium sulfide suspension for treatment of transplanted human liver carcinoma in nude mice

Hepatocellular carcinoma (HCC) is one of the most common malignancies in China. Direct intratumoral injection of nonremovable radioactive material has been widely studied because it could deliver high doses of radiation to target sites and minimize radiation leakage to non-target organs or tissues. Thirty nude mice bearing SMMC 7721 human liver carcinoma were used for the biodistribution study after intratumoral injection of [(188)Re]rhenium sulfide suspension or sodium [(188)Re]perrhenate solution. Another 30 tumor-bearing mice were divided into six groups, four groups of which were treated with a 0.1 ml [(188)Re]rhenium sulfide suspension at doses of 3.7, 7.4, 18.5, 29.6 MBq by a single intratumoral injection. For control studies, to study the tumor inhibiting ratio, the remaining two groups were injected with nonradioactive rhenium sulfide suspension and Hanks' balanced salt solution, respectively. The injections were repeated 6 days later. The retention percentages of radioactivity (%ID) in tumors injected with [(188)Re]rhenium sulfide suspension were 90.96+/-6.63%, 86.09+/-22.58% and 87.62+/-13.97% at 1, 24 and 48 h, respectively. Tumor inhibition ratios are as high as 89% when the outer space of tumor (0.5-0.6 cm from center) received about 507.6 Gy doses. Intratumoral injection of [(188)Re]rhenium sulfide suspension results in high tumor retention indicating this approach has strong potential for the treatment of hepatic carcinoma.     

18F-Fluoroerythronitroimidazole radiation dosimetry in cancer studies.

18F-Fluoroerythronitromidazole (FETNIM) is a new promising PET tracer for imaging tumor hypoxia. Accurate radiation dosimetry is important for estimating absorbed radiation doses to patients and for calculating the allowable injected dose. METHODS: Radiation absorbed doses were estimated from PET scans obtained on cancer patients on the basis of the MIRD procedure. Dynamic acquisition data was obtained from the thorax, abdomen, and head and neck regions. The tracer was injected intravenously and mean injected activity was 366 MBq (range, 288-385 MBq). Arterial blood was continuously assayed over dynamic PET imaging. The bladder wall dose was evaluated from the voided urine activity measurements. RESULTS: The effective dose to a 70-kg adult was 0.015 or 0.019 mSv/MBq, calculated on 2- or 4-h voiding intervals, respectively. The critical organ proved to be the urinary bladder wall, with a highest absorbed dose of 0.062 or 0.127 mGy/MBq depending on the voiding schedule as described above. Absorbed doses in all other organs were at least 5-fold smaller than the bladder wall doses. CONCLUSION: With an injected activity of 370 MBq (18)F-FETNIM, the radiation doses are generally comparable with those of other related radionuclide imaging procedures. Specifically, in comparison with (18)F-fluoromisonidazole, the absorbed doses of (18)F-FETNIM are equal. However, special attention should be given to adequate hydration and voiding to limit the relatively high exposure of the critical organ, bladder wall, to (18)F-FETNIM.     

Local injection of the 90Y-labelled peptidic vector DOTATOC to control gliomas of WHO grades II and III: an extended pilot study

We have previously presented preliminary observations on targeting somatostatin receptor-positive malignant gliomas of all grades by local injection of the radiolabelled peptidic vector 90Y-DOTATOC. We now report on our more thorough clinical experience with this novel compound, focussing on low-grade and anaplastic gliomas. Small peptidic vectors have the potential to target invisible infiltrative disease within normal surrounding brain tissue, thereby opening a window of opportunity for early intervention. Five progressive gliomas of WHO grades II and III and five extensively debulked low-grade gliomas were treated with varying fractions of 90Y-DOTATOC. The vectors were locally injected into the resection cavity or into solid tumour. The activity per single injection ranged from 555 to 1,875 MBq, and the cumulative activity from 555 to 7,030 MBq, according to tumour volumes and eloquence of the affected brain area, yielding dose estimates from 76+/-15 to 312+/-62 Gy. Response was assessed by the clinical status, by steroid dependence and, every 4-6 months, by magnetic resonance imaging and fluorine-18 fluorodeoxyglucose positron emission tomography. In the five progressive gliomas, lasting responses were obtained for at least 13-45 months without the need for steroids. Radiopeptide brachytherapy had been the only modality applied to counter tumour progression. Interestingly, we observed the slow transformation of a solid, primarily inoperable anaplastic astrocytoma into a resectable multi-cystic lesion 2 years after radiopeptide brachytherapy. Based on these observations, we also assessed the feasibility of local radiotherapy following extensive debulking, which was well tolerated. Targeted beta-particle irradiation based on diffusible small peptidic vectors appears to be a promising modality for the treatment of malignant gliomas.