Indium-111-DOTA-lanreotide: biodistribution, safety and radiation absorbed dose in tumor patients

Imaging with radiolabeled somatostatin/vasoactive intestinal peptide analogs has recently been established for the localization diagnosis of a variety of human tumors including neuroendocrine tumors, intestinal adenocarcinomas and lymphomas. This study reports on the biodistribution, safety and radiation absorbed dose of 111In-1,4,7,10-tetraazacyclododecane-N,N',N",N'-tetraacetic acid (DOTA)-lanreotide, a novel peptide tracer, which identifies hSST receptor (R) subtypes 2 through 5 with high affinity, and hSSTR1 with low affinity. METHODS: The tumor localizing capacity of 111In-DOTA-lanreotide was initially investigated in 10 patients (3 lymphomas, 5 carcinoids and 2 intestinal adenocarcinomas). Indium-111 -DOTA-lanreotide was then administered to 14 cancer patients evaluated for possible radiotherapy with 90Y-DOTA-lanreotide (8 neuroendocrine tumors, 4 intestinal adenocarcinomas, 1 Hodgkin lymphoma and 1 prostate cancer). After intravenous administration of 111In-DOTA-lanreotide (approximately = 150 MBq; 10 nmol/patient), sequential images over one-known tumor site were recorded during the initial 30 min after peptide application. Thereafter, whole-body images were acquired in anterior and posterior views up to 72 hr postinjection. Dosimetry calculations were performed on the basis of scintigraphic data, urine, feces and blood activities. A comparison with 111In-DTPA-D-Phe1-octreotide (111In-OCT) scintigraphy was performed in 8 of the patients. RESULTS: After an initial rapid blood clearance [results of biexponential fits: T(eff1) 0.4 min (fraction a1 80%) and T(eff2) 13 min (fraction a2 14%)], the radioactivity was excreted into the urine and amounted to 42% +/- 3% of the injected dose (%ID) within 24 hr and 62% +/- 6%ID within 72 hr after injection of 111In-DOTA-lanreotide. In all patients, tumor sites were visualized during the initial minutes after injection of 111In-DOTA-lanreotide. The mean radiation absorbed dose amounted to 1.2 (range 0.21-5.8) mGy/MBq for primary tumors and/or metastases. The effective half-lives of 111In-DOTA-lanreotide in the tumors were T(eff1) 4.9 +/- 2.2 and T(eff2) 37.6 +/- 6.6 hr, and the mean residence time tau was 1.8 hr. The highest radiation absorbed doses were calculated for the spleen (0.39 +/- 0.13 mGy/MBq), kidneys (0.34 +/- 0.08 mGy/MBq), urinary bladder (0.21 +/- 0.03 mGy/MBq) and liver (0.16 +/- 0.04 mGy/MBq). The effective dose was 0.11 +/- 0.01 (range 0.09-0.12) mSv/MBq. During the observation period of 72 hr, no side effects were noted after 111In-DOTA-lanreotide application. The 111In-DOTA-lanreotide radiation absorbed tumor dose was significantly higher (ratio 2.25 +/- 0.60, p < 0.01) when directly compared with 111In-OCT. CONCLUSION: Indium-111 -DOTA-lanreotide shows a high tumor uptake for a variety of different human tumor types, has a favorable dosimetry over 111In-OCT and is clinically safe.     

Human biodistribution and dosimetry of iodine-123-fluoroalkyl analogs of beta-CIT

Two new N-omega-fluoroalkyl analogs of [123I]2beta-carbomethoxy-3beta-(4-iodophenyl)tropane ([123I]beta-CIT), the fluoroethyl and fluoropropyl compounds ([123I]FE-CIT and [123I]FP-CIT, respectively), have been shown to have faster kinetics and better selectivity for the dopamine transporter than [123I]beta-CIT. We examined the organ biodistribution and radiation safety of these two compounds in six healthy volunteers who received an injection with each of the two compounds 2 weeks apart. Data were obtained on the Strichman 860 whole-body scanner. Transmission scans were obtained in all subjects prior to the injection of the radiotracer with a line source and used to derive organ-specific attenuation correction factors. Whole-body planar images were acquired every hour for the first 6 h, and at 24 h. Attenuation-corrected regional conjugate counts were converted into units of activity using a calibration factor obtained for each subject by dividing whole-body conjugate decay-corrected counts from the first acquisition by the injected activity. Radiation dose estimates were on average higher for [123I]CIT-FE than for [123I]CIT-FP, with the lower large intestine receiving the highest exposure: 0.15+/-13% mGy/MBq (mean +/-COV) and 0.12+/-14% mGy/MBq for [123I]FE-CIT and [123I]FP-CIT, respectively, followed by the upper large intestine and the spleen.     

Radiochemical purity of iodine-131 labelled metaiodobenzylguanidine infusion fluids: a report from clinical practice

Iodine-131 labelled metaiodobenzylguanidine ([131I]MIBG) has a diagnostic and therapeutic role in the management of neural crest tumours, particularly neuroblastoma, malignant phaeochromocytoma and paraganglioma. With therapeutic amounts of [131I]MIBG it is essential that the amount of free [131I]iodide, the most important impurity, is known. In clinical practice the percentage of free [131I]iodide seen in a [131I]MIBG infusion concentrate increased from 2.2% +/- 0.67% to 3.6% +/- 0.39% (mean +/- SD; n = 23) 1 day after production. At the time of use the percentage of free [131I]iodide was always below our upper limit of acceptance of 5%. Since 5% of free [131I]iodide is within practical reach in our environment, a higher percentage at the time of preadministration quality control is not accepted in the Netherlands Cancer Institute.     

Maximum-tolerated dose, toxicity, and efficacy of (131)I-Lym-1 antibody for fractionated radioimmunotherapy of non-Hodgkin's lymphoma

PURPOSE: Lym-1, a monoclonal antibody that preferentially targets malignant lymphocytes, has induced remissions in patients with non-Hodgkin's lymphoma (NHL) when labeled with iodine 131 ((131)I). Based on the strategy of fractionating the total dose, this study was designed to define the maximum-tolerated dose (MTD) and efficacy of the first two, of a maximum of four, doses of (131)I-Lym-1 given 4 weeks apart. Additionally, toxicity and radiation dosimetry were assessed. MATERIALS AND METHODS: Twenty patients with advanced NHL entered the study a total of 21 times. Thirteen (62%) of the 21 entries had diffuse large-cell histologies. All patients had disease resistant to standard therapy and had received a mean of four chemotherapy regimens. (131)I-Lym-1 was given after Lym-1 and (131)I was escalated in cohorts of patients from 40 to 100 mCi (1.5 to 3.7 GBq)/m2 body surface area. RESULTS: Mean radiation dose to the bone marrow from body and blood (131)I was 0.34 (range, 0. 1 6 to 0.63) rad/mCi (0.09 mGy/MBq; range, 0.04 to 0.17 mGy/ MBq). Dose-limiting toxicity was grade 3 to 4 thrombocytopenia with an MTD of 100 mCi/m2 (3.7 GBq/m2) for each of the first two doses of (131)I-Lym-1 given 4 weeks apart. Nonhematologic toxicities did not exceed grade 2 except for one instance of grade 3 hypotension. Ten (71 %) of 14 entries who received at least two doses of (131)I-Lym-1 therapy and 11 (52%) of 21 total entries responded. Seven of the responses were complete, with a mean duration of 14 months. All three entries in the 100 mCi/m2 (3.7 MBq/m2) cohort had complete remissions (CRs). All responders had at least a partial remission (PR) after the first therapy dose of (131)I-Lym-1. CONCLUSION: (131)I-Lym-1 induced durable remissions in patients with NHL resistant to chemotherapy and was associated with acceptable toxicity. The nonmyeloablative MTD for each of the first two doses of (131)I-Lym-1 was 100 mCi/m2 (total, 200 mCi/m2) (3.7 GBq/m2; total, 7.4 GBq/m2).     

Fluorine-18-fluoromisonidazole radiation dosimetry in imaging studies

Fluoromisonidazole (FMISO), labeled with the positron emitter 18F, is a useful hypoxia imaging agent for PET studies, with potential applications in patients with tumors, cardiovascular disease and stroke. METHODS: Radiation doses were calculated in patients undergoing imaging studies to help define the radiation risk of FMISO-PET imaging. Time-dependent concentrations of radioactivity were determined in blood samples and PET images of patients following intravenous injection of [18F]FMISO. Radiation absorbed doses were calculated using the procedures of the Medical Internal Radiation Dose (MIRD) committee, taking into account the variation in dose based on the distribution of activities observed in the individual patients. As part of this study we also calculated an S value for brain to eye. Effective dose equivalent was calculated using ICRP 60 weights. RESULTS: Effective dose equivalent was 0.013 mSv/MBq in men and 0.014 mSv/MBq in women. Individual organ doses for women were not different from men. Assuming bladder voiding at 2- or 4-hr intervals, the critical organ that received the highest dose was the urinary bladder wall (0.021 mGy/MBq with 2-hr voiding intervals or 0.029 mGy/MBq with 4-hr voiding intervals). CONCLUSION: The organ doses for [18F]FMISO are comparable to those associated with other commonly performed nuclear medicine tests and indicate that potential radiation risks associated with this study are within generally accepted limits.     

Radiation dose estimates of 186Re-hydroxyethylidene diphosphonate for palliation of metastatic osseous lesions: an animal model study

A common complication in patients with breast or prostate cancer is bone metastases causing pain. New radionuclide therapy methods have recently been proposed for palliation, including 186Re-hydroxyethylidene diphosphonate (186Re-HEDP). This paper reports on the local development of 186Re-HEDP and the biodistribution studied in animals for eventual use in patients. Adult dose was computed assuming a 70 kg standard man. The 186Re was labelled to HEDP using standard techniques. The biodistribution in five Chacma baboons (Papio ursinus) was studied. Doses ranging from 39.4 to 44.9 MBq kg(-1) (mean 43.6 +/- 2.8 MBq kg[-1]) were administered, corresponding to an adult human dose of 2960 MBq (80 mCi). Whole-body images of the animals were obtained with a dual-headed scintillation camera on an hourly basis for 6 h post-injection and then daily for 3 days. The bone, soft tissue, kidneys and urinary bladder were considered source organs and data from these organs were used in a compartmental model to obtain the mean residence times of the radionuclide in the different source organs. Radiation dose estimates for 186Re-HEDP were subsequently obtained with the MIRDOSE 3 program. The estimated absorbed radiation doses to some of the organs (expressed in mGy MBq[-l]) were as follows: bone surface 1.69; kidneys 0.09; liver 0.04; ovaries 0.04; red marrow 0.75; total body 0.12; urinary bladder wall 0.43. 186Re-HEDP yielded an effective dose of 0.17 mSv MBq(-1). The radiation dose delivered to the bone marrow in this study did not cause any detrimental effect to the baboons, indicating that locally produced 186Re-HEDP is suitable for clinical use.     

No-carrier-added synthesis of meta-[131I]iodobenzylguanidine

No-carrier-added meta-[131I]iodobenzylguanidine ([131I]MIBG) was prepared starting with two different metallated precursors. Attempted preparation of 3-(tri-n-butylstannyl)benzylguanidine was not successful. An alternate two-step strategy using 3-(tri-n-butylstannyl)benzylamine could be used to prepare radio-iodinated [131I]MIBG in an overall radiochemical yield of 30-33%. Synthesis of [131I]MIBG via the radioiododesilylation of 3-trimethylsilylbenzylguanidine was also investigated. Yields were dependent on temperature, precursor concentration, solvent and nature of the oxidant. Radiochemical yields of 90% were obtained in 5 min at room temperature using either N-chlorosuccinimide or hydrogen peroxide in trifluoroacetic acid as oxidants. The percentage of specific binding in vitro of no-carrier-added MIBG to SK-N-SH neuroblastoma cells remained constant over a 2 log activity range, while the binding of MIBG prepared by isotopic exchange dropped by a factor of seven. In normal mice, heart and adrenal uptake of no-carrier-added [131I]MIBG was found to be higher than that of [131I]MIBG prepared by isotopic exchange.     

Toxicity to neuroblastoma cells and spheroids of benzylguanidine conjugated to radionuclides with short-range emissions

Radiolabelled meta-iodobenzylguanidine (MIBG) is selectively taken up by tumours of neuroendocrine origin, where its cellular localization is believed to be cytoplasmic. The radiopharmaceutical [131I]MIBG is now widely used in the treatment of neuroblastoma, but other radioconjugates of benzylguanidine have been little studied. We have investigated the cytotoxic efficacy of beta, alpha and Auger electron-emitting radioconjugates in treating neuroblastoma cells grown in monolayer or spheroid culture. Using a no-carrier-added synthesis route, we produced 123I-, 125I-, 131I- and 211At-labelled benzylguanidines and compared their in vitro toxicity to the neuroblastoma cell line SK-N-BE(2c) grown in monolayer and spheroid culture. The Auger electron-emitting conjugates ([123I]MIBG and [125I]MIBG) and the alpha-emitting conjugate ([211At]MABG) were highly toxic to monolayers and small spheroids, whereas the beta-emitting conjugate [131I]MIBG was relatively ineffective. The Auger emitters were more effective than expected if the cellular localization of MIBG is cytoplasmic. As dosimetrically predicted however, [211At]MABG was found to be extremely potent in terms of both concentration of radioactivity and number of atoms ml(-1) administered. In contrast, the Auger electron emitters were ineffective in the treatment of larger spheroids, while the beta emitter showed greater efficacy. These findings suggest that short-range emitters would be well suited to the treatment of circulating tumour cells or small clumps, whereas beta emitters would be superior in the treatment of subclinical metastases or macroscopic tumours. These experimental results provide support for a clinical strategy of combinations ('cocktails') of radioconjugates in targeted radiotherapy.     

Fluorine-18-fluoro-L-DOPA dosimetry with carbidopa pretreatment

This article presents dosimetry based on the measurement of fluoro-DOPA activity in major tissues and in the bladder contents in humans after oral pretreatment with 100 mg carbidopa. METHODS: Bladder activity was measured continuously by external probe and calibrated using complete urine collections. Quantitative dynamic PET scans provided time-activity curves for the major organs. Bladder wall dosimetry was calculated using the methods of MIRD Pamphlet No. 14. Effective dose was calculated as described in ICRP Publication 60. RESULTS: Mean absorbed dose to the bladder wall surface per unit administered activity was 0.150 mGy/MBq (0.556 rad/mCi) with the realistic void schedule used in our studies. The dose was 0.027 mGy/MBq (0.101 rad/mCi) to the kidneys, 0.0197 mGy/MBq (0.0728 rad/mCi) to the pancreas, and 0.0186 mGy/MBq (0.0688 rad/mCi) to the uterus. Absorbed doses to other organs were an order of magnitude or more lower than the bladder, 0.009-0.015 mGy/MBq. The effective dose per unit administered activity was 0.0199 mSv/MBq (0.0735 rem/mCi.) CONCLUSION: Urinary excretion of fluoro-DOPA was altered significantly by pretreatment with carbidopa. In general, any manipulation of tracer metabolism in the body should be expected to produce changes in biodistribution and dosimetry. The largest radiation dose was to the bladder wall, for which our estimate was one-fifth of that from the original report. The methods used reflect realistic urinary physiology and typical use of this tracer. The principles of MIRD Pamphlet No. 14 should be used in planning studies using tracers excreted in the urine to minimize the absorbed dose.     

Dosimetric analysis of chimeric monoclonal antibody cMOv18 IgG in ovarian carcinoma patients after intraperitoneal and intravenous administration

In this study the potential of intraperitoneal (i.p.) and intravenous (i.v.) administration of chimeric iodine-131-labelled MOv18 IgG for radioimmunotherapy was determined. The dosimetry associated with both routes of administration of cMOv18 IgG was studied in patients. Eight patients suspected of having ovarian carcinoma received 150 MBq 131I-cMOv18 IgG i.p. Blood and urine were collected and serial gamma camera images were acquired. Another group of four patients received 7.5 MBq 131I-cMOv18 IgG i.v. For all patients, tissue biopsies were obtained at surgery. Activity in the blood after i.p. administration was described by a bi-exponential curve with a mean uptake and elimination half-life of 6.9+/-3.2 h and 160+/-45 h, respectively. For i.v. infusion the mean half-life for the elimination phase was 103+/-12 h. Cumulative excretion in the urine was 17%+/-3% ID and 21%+/-7% ID in 96 h for i.p. and i.v. administration, respectively. Scintigraphic images after i.p. administration showed accumulation in ovarian cancer lesions, while all other tissues showed decreasing activity with time. Tumour uptake determined in the ovarian cancer tissue specimens ranged from 3.4% to 12.3% ID/kg for i.p. administration and from 3.6% to 5.4% ID/kg for i.v. administration. Dosimetric analysis of the data indicated that 1.7-4.3 mGy/MBq and 1.7-2.2 mGy/MBq can be guided to solid or ascites cells after i.p. and i.v. administration, respectively. Assuming that an absorbed dose to the bone marrow of 2 Gy will be dose limiting, a total activity of 4.1 GBq 131I-cMOv18 IgG can be administered safely via the i.p. route and 3.5 GBq via the i.v. route. At this maximal tolerated dose, a maximum absorbed dose to 1-g tumours in the peritoneal cavity of 18 and 8 Gy can be reached after i.p. and i.v. administration, respectively. For the i. p. route of administration, dose estimates for the tumour are even higher when the electron dose of the peritoneal activity is also taken into account: total doses to the tumour of 30 Gy and 22 Gy will be absorbed at the tumour surface and at 0.2 mm depth, respectively. In conclusion, therapeutic tumour doses can be achieved with 131I-cMOv18 IgG in patients with intraperitoneal ovarian cancer lesions with no normal organ toxicity. The i.p. route of administration seems to be preferable to i.v. administration.     

Phase I/II clinical radioimmunotherapy with an iodine-131-labeled anti-carcinoembryonic antigen murine monoclonal antibody IgG

The aim of this study was to determine, in a Phase I/II clinical trial, the pharmacokinetics, dosimetry and toxicity, as well as antitumor activity, of the 131I-labeled murine anti-carcinoembryonic antigen (CEA) monoclonal antibody, NP-4 (IgG1 subtype). METHODS: A total of 57 patients with CEA-expressing tumors (29 colorectal, 9 lung, 7 pancreas, 6 breast and 4 medullary thyroid cancer patients), mostly in very advanced stages, were treated. The patients underwent a diagnostic study (1-3 mg of IgG and 8-30 mCi of 131I) to assess tumor targeting and to estimate dosimetry, followed by the therapeutic dose (4-23 mg and 44-268 mCi), based on the radiation dose to the red marrow. Imaging was performed from 4-240 hr postinjection (planar and SPECT). Blood and whole-body clearance were determined; radiation doses were calculated by the Medical Internal Radiation Dose scheme. RESULTS: Red marrow doses ranged from 45 to 706 cGy, and whole-body doses ranged from 31 to 344 cGy. Differences in pharmacokinetics were found between different types of CEA-producing tumors: blood T 1/2 was significantly lower in colorectal cancer when compared to all other tumor types (21.4 +/- 11.1 hr versus 35.8 +/- 13.2 hr, p < 0.01), as was also whole-body t 1/2. Myelotoxicity was dose-limiting, and its severity was related to the types of prior therapy and extent of bone marrow involvement. In patients without prior radiation or chemotherapy, marrow doses as high as 600 cGy were tolerated without evidence of dose-limiting toxicity. No major toxicity to other organs was observed. Tumor doses were inversely related to the tumor mass and ranged between 2 and 218 cGy/mCi. Modest antitumor effects were seen in 12 of 35 assessable patients (1 partial remission, 4 minor/mixed responses and 7 with stabilization of previously rapidly progressing disease). CONCLUSION: These results suggest that prior chemotherapy or external beam radiation is an important risk factor for the development of hematological toxicity in radioimmunotherapy and that higher radiation doses may be delivered to tumors of patients without prior therapy compromising the bone marrow reserve. The different and, in the individual cases, unpredictable clearance rates suggest the necessity of dosimetry-based treatment planning rather than mCi/m2 dosing. Small tumors seem to be more suitable for radioimmunotherapy because of their favorable dosimetry, but to achieve better therapeutic results in patients with bulky disease, the application of higher, potentially myeloablative doses is indicated.     

Dosimetry of copper-64-labeled monoclonal antibody 1A3 as determined by PET imaging of the torso

We present biodistribution and dosimetry results for 64Cu-benzyl-TETA-MAb 1A3 from 15 human subjects injected with this tracer as determined by serial PET imaging of the torso. METHODS: PET imaging was used to quantify in vivo tracer biodistribution at two time points after injection. Absorbed dosimetry calculated using MIRD-11 and the updated MIRDOSE3 was compared with estimates obtained using rat biodistribution data. RESULTS: By measuring activity concentrations in the torso, and extrapolating for the whole body using standard organ and tissue volumes, we were able to account for 93% of the injected radiopharmaceutical over a range of imaging times from 0 to 36 hr postinjection. Based on PET imaging and the MIRD-11 schema, the liver and spleen are the critical organs with average absorbed doses of 0.12 and 0.10 mGy/MBq (0.44 and 0.39 rad/mCi). The revised MIRDOSE3 scheme yields similar values for these and other organs but also results in a dose of 0.14 mGy/MBq (0.53 rad/mCi) to the heart wall. In the rat, the large intestine is the critical organ at 0.14 mGy/MBq (0.52 rad/mCi), while liver and kidneys each receive 0.11 mGy/MBq (0.41 rad/mCi). Some disparities in absorbed doses determined by these methods are evident but are a result of dissimilar biodistributions in rats and humans. For most organs, rat extrapolated values are higher than the human measurements with PET. CONCLUSION: This study shows that torso PET imaging can quantitatively measure the whole-body biodistribution of a radiopharmaceutical as long as it has relatively slow pharmacokinetics.     

Phase I/II radioimmunotherapy trial with iodine-131-labeled monoclonal antibody G250 in metastatic renal cell carcinoma

This Phase I/II radioimmunotherapy study was carried out to determine the maximum tolerated dose (MTD) and therapeutic potential of 131I-G250. Thirty-three patients with measurable metastatic renal cell carcinoma were treated. Groups of at least three patients received escalating amounts of 1311I (30, 45, 60, 75, and 90 mCi/m2) labeled to 10 mg of mouse monoclonal antibody G250, administered as a single i.v. infusion. Fifteen patients were studied at the MTD of activity. No patient had received prior significant radiotherapy; one had received prior G250. Whole-body scintigrams and single-photon emission computed tomography images were obtained in all patients. There was targeting of radioactivity to all known tumor sites that were > or =2 cm. Reversible liver function test abnormalities were observed in the majority of patients (27 of 33 patients). There was no correlation between the amount of 131I administered or hepatic absorbed radiation dose (median, 0.073 Gy/mCi) and the extent or nature of hepatic toxicity. Two of the first six patients at 90 mCi/m2 had grade > or =3 thrombocytopenia; the MTD was determined to be 90 mCi/m2 131I. Hematological toxicity was correlated with whole-body absorbed radiation dose. All patients developed human antimouse antibodies within 4 weeks posttherapy; retreatment was, therefore, not possible. Seventeen of 33 evaluable patients had stable disease. There were no major responses. On the basis of external imaging, 131I-labeled mouse monoclonal antibody G250 showed excellent localization to all tumors that were > or =2 cm. Seventeen of 33 patients had stable disease, with tumor shrinkage observed in two patients. Antibody immunogenicity restricted therapy to a single infusion. Studies with a nonimmunogenic G250 antibody are warranted.     

Acute liver necrosis induced by iodine-131-MIBG in the treatment of metastatic carcinoid tumors

Iodine-131-metaiodobenzylguanidine (MIBG) is used in the treatment of carcinoid tumors. Temporary palliation with complete subjective symptomatic response has been reported in these patients. This treatment is usually well tolerated and side-effects are generally limited to nausea, mild hepatic toxicity with spontaneous recovery and temporary myelosuppression. Our case report shows that repeated treatment with [131I]MIBG in a patient with extensive carcinoid liver metastasis may cause severe hepatic toxicity leading to death. Factors such as concomitant use of 5-fluorouracil and the progressive nature of the disease may have contributed to this event.     

Yttrium-90-DOTA-peptide-chimeric L6 radioimmunoconjugate: efficacy and toxicity in mice bearing p53 mutant human breast cancer xenografts

The novel radioimmunoconjugate, 90Y-DOTA-peptide-chimeric L6 (ChL6), was designed to reduce radiation to critical normal tissues with an exceptionally stable 90Y chelate moiety and a biodegradable linker. Human breast cancer tumors (HBT 3477) in mice were treated with 90Y-DOTA-peptide-ChL6 to examine the effects of increasing dose on the therapeutic efficacy and toxicity of this new agent. METHODS: Groups of athymic mice bearing HBT 3477 xenografts received 4.1- to 14.1-MBq doses of 90Y-DOTA-peptide-ChL6 intravenously. The lethal dose (LD)(50/30), general well-being (weight loss), hematotoxicity and therapeutic efficacy were studied. RESULTS: The LD(50/30) was 12.8 MBq, which corresponded to doses of 17.9 and 50.9 Gy to the total body and tumor (200 mm3), respectively. Deaths were associated with hematotoxicity; no deaths occurred at doses of 9.6 MBq or less. At sublethal doses, the rate of tumor response (cures +/- complete responses + partial responses) increased with increasing dose: 4.1 MBq, 27%; 5.9 MBq, 41%; 8.5 MBq, 69%; and 9.6 MBq, 79% (maximum tolerated dose, MTD). In mice receiving doses of 4.1-9.6 MBq, 6 of 74 (8%) of tumors were cured. Increasing the 90Y dose led to smaller tumor size at nadir and longer tumor regrowth delay but no increase in cure. Although the HBT 3477 p53 gene was found to be mutant resulting in p53 protein not binding DNA breaks, tumors at MTD demonstrated evidence of apoptosis. CONCLUSION: In the human breast cancer athymic mouse model, 90Y-DOTA-peptide-ChL6 had a high therapeutic index and LD(50/30) leading to a 79% response rate at the MTD. The evidence of apoptosis as a mechanism for this tumor response in p53 mutant breast cancer warrants further studies because these observations are relevant to the treatment of lethal breast cancer.     

Evaluation of external radiation exposure rate from radioiodine-treated hyperthyroid patients and radiation safety considerations

Hyperthyroid patients treated with radioiodine (131I) pose an external radiation risk to individuals who come into close contact with them. In order to determine changes in levels of external radiation with time in relation to the dose administered, 38 hyperthyroid patients being treated with 131I were evaluated Thyroid uptake, plasma T3, T4 and TSH levels were measured prior to treatment. Using a Geiger-Muller probe, levels of external radiation were measured at distances of 0.3, 0.6, 1.0 and 2.0 m from the patient -at the level at which the maximum activity was recorded -30 min, 1, 3, 7 and 10 days post-therapy. The patients were split into two groups. Group I comprised 22 patients treated with < or = 370 MBq 131I, 5 (23%) of whom registered > 0.46 mC kg-1 at a distance of 1.0 m 30 min post-therapy. Group II comprised 16 patients treated with > 370 MBq 131I, 13 (81%) of whom registered 0.46 mC kg-1 at a distance of 1.0 m one day post-therapy. At 3 days in Group I and 7 days in Group II, the estimated total radiation exposure rates were found to exceed the 1994 US Nuclear Regulatory Commission dose limits for children and pregnant women. Based on the results obtained, we present some guidelines intended to prevent the public from unnecessary radiation exposures.     

1-[Carbon-11]-glucose radiation dosimetry and distribution in human imaging studies

1-[Carbon-11]-D-glucose ([11C]-glucose) is an important imaging agent for PET studies that have been used to study the normal brain, encephalitis, epilepsy, manic-depressive disorder, schizophrenia and brain tumors. METHODS: Dosimetry estimates were calculated in subjects undergoing imaging studies to help define the radiation risk of [11C]-glucose PET imaging. Time-dependent radioactivity concentrations in normal tissues in 33 subjects after intravenous injection of [11C]-glucose were obtained by PET imaging. Radiation absorbed doses were calculated according to the procedures of the Medical Internal Radiation Dose (MIRD) committee along with the variation in dose based on the calculated standard deviation of activity distribution seen in the individual patients. RESULTS: Total body exposure was a median of 3.0 microGy/MBq in men and 3.8 microGy/MBq in women. The effective dose equivalent was 3.8 microGy/ MBq in men and 4.8 microGy/MBq in women. The critical organs were those that typically take up the most glucose (brain, heart wall and liver). CONCLUSION: The organ doses reported here are small and comparable to those associated with other commonly performed nuclear medicine tests and indicate that potential radiation risks associated with this radiotracer are within generally accepted limits.     

Iodine-131-anti-B1 radioimmunotherapy for B-cell lymphoma

PURPOSE: The CD20 B-lymphocyte surface antigen expressed by B-cell lymphomas is an attractive target for radioimmunotherapy, treatment using radiolabeled antibodies. We conducted a phase I dose-escalation trial to assess the toxicity, tumor targeting, and efficacy of nonmyeloablative doses of an anti-CD20 monoclonal antibody (anti-B1) labeled with iodine-131 (131I) in 34 patients with B-cell lymphoma who had failed chemotherapy. PATIENTS AND METHODS: Patients were first given tracelabeled doses of 131I-labeled anti-B1 (15 to 20 mg, 5 mCi) to assess radiolabeled antibody biodistribution, and then a radioimmunotherapeutic dose (15 to 20 mg) labeled with a quantity of 131I that would deliver a specified centigray dose of whole-body radiation predicted by the tracer dose. Whole-body radiation doses were escalated from 25 to 85 cGy in sequential groups of patients in 10-cGy increments. To evaluate if radiolabeled antibody biodistribution could be optimized, initial patients were given one or two additional tracer doses on successive weeks, each dose preceded by an infusion of 135 mg of unlabeled anti-B1 one week and 685 mg the next. The unlabeled antibody dose resulting in the most optimal tracer biodistribution was also given before the radioimmunotherapeutic dose. Later patients were given a single tracer dose and radioimmunotherapeutic dose preceded by infusion of 685 mg of unlabeled anti-B1. RESULTS: Treatment was well tolerated. Hematologic toxicity was dose-limiting, and 75 cGy was established as the maximally tolerated whole-body radiation dose. Twenty-eight patients received radioimmunotherapeutic doses of 34 to 161 mCi, resulting in complete remission in 14 patients and a partial response in eight. All 13 patients with low-grade lymphoma responded, and 10 achieved a complete remission. Six of eight patients with transformed lymphoma responded. Thirteen of 19 patients whose disease was resistant to their last course of chemotherapy and all patients with chemotherapy-sensitive disease responded. The median duration of complete remission exceeds 16.5 months. Six patients remain in complete remission 16 to 31 months after treatment. CONCLUSION: Nonmyeloablative radioimmunotherapy with 131I-anti-B1 is associated with a high rate of durable remissions in patients with B-cell lymphoma refractory to chemotherapy.     

Dynamic distribution and dosimetric evaluation of human non-specific immunoglobulin G labelled with 111In or 99Tcm

This study presents data on the dynamic distribution and dosimetry of 111In- and 99Tcm-labelled human non-specific immunoglobulin G (IgG), two recently developed radiopharmaceuticals for the detection of infection and inflammation. Five healthy volunteers were injected with 20-75 MBq 111In-IgG and seven patients were injected with 740 MBq 99Tcm-hydrazinonicotinamide derivative (HYNIC)-IgG. Blood samples, urine and feces were collected. Whole-body gamma camera imaging studies were performed. The activity in source organs was quantified using the conjugate view counting method and a partial background subtraction technique. Dosimetric calculations were performed using the MIRD technique. For 111In-IgG, the mean biological half-times in the blood were 0.90 and 46 h for the a- and b-phase, respectively. For 99Tcm-HYNIC-IgG, these half times were 0.46 and 45 h. For 111In-IgG, the mean cumulative urinary excretion in the first 48 h was 18% of the injected dose, while excretion in the feces was less than 2% of the injected dose. For 99Tcm-HYNIC-IgG, the whole-body retention was always 100% up to 24 h. The mean absorbed doses in the liver, spleen, kidneys, red marrow and testes from 111In-IgG were 0.8, 0.7, 1.2, 0.3 and 0.4 mGy MBq-1 respectively. The mean absorbed doses for 99Tcm-HYNIC-IgG to these organs were 16, 24, 15, 10 and 22 mu Gy MBq-1 respectively. The mean effective dose was 0.25 mSv MBq-1 and 8.4 mu Sv MBq-1 for 111In-IgG and 99Tcm-HYNIC-IgG respectively. In conclusion, the radiation absorbed doses for both 111In-IgG and 99Tcm-HYNIC-IgG are low and, therefore, these radiopharmaceuticals can be administered safely from a radiation risk perspective.     

Pheochromocytomas that do not accumulate metaiodobenzylguanidine: localization with PET and administration of FDG

Many imaging methods can be used to detect pheochromocytoma, but some tumors are not detected with conventional modalities. To explore the possible usefulness of positron emission tomography (PET) after administration of 2-[fluorine-18]-fluoro-2-deoxy-D-glucose (FDG) to localize pheochromocytoma in patients with false-negative scintigrams obtained after administration of metaiodobenzylguanidine (MIBG), FDG was administered and PET was performed in two adult patients with pheochromocytomas that had never been localized despite administration of MIBG. In both patients, images were obtained dynamically for 50 minutes; then a limited truncal sequence was performed. PET enabled correct localization of the tumors. In patient 1, a tumor that had not been detected for 21 years was localized in the middle mediastinum; in patient 2, a pheochromocytoma was detected in the right adrenal gland. PET performed after administration of FDG may be useful for localization of pheochromocytomas that do not accumulate MIBG.