Factors affecting 131I-Lym-1 pharmacokinetics and radiation dosimetry in patients with non-Hodgkin's lymphoma and chronic lymphocytic leukemia.

Lym-1, a monoclonal antibody that preferentially targets malignant lymphocytes, has induced therapeutic responses in patients with non-Hodgkin's lymphoma (NHL) and chronic lymphocytic leukemia (CLL) when labeled with 131I. Responders had statistically significant prolongation of survival compared with nonresponders. The nonmyeloablative, maximum tolerated dose for each of two doses of 131I-Lym-1 was 3.7 GBq/m2 (total 7.4 GBq/m2 [100 mCi/m2, total 200 mCi/m2]) of body surface area. The purpose of this study was to determine the pharmacokinetics and radiation dosimetry for the initial 131I-Lym-1 therapy dose in patients with NHL and CLL and to compare tumor dosimetry with 131I-Lym-1 dosing and other patient parameters. METHODS: Fifty-one patients with stage 3 or 4 lymphoma were treated with 131I-Lym-1 (0.74-8.04 GBq [20-217 mCi]) in either a maximum tolerated dose (MTD) or low-dose (LD) trial. Total Lym-1 given to each patient was sufficient in all instances to exceed the threshold required for stable pharmacokinetics. Quantitative imaging and physical examination, including caliper and CT measurement of tumor size and analysis of blood, urine and feces, were performed for a period of 7 to 10 d after infusion to assess pharmacokinetics and radiation dosimetry. Clinical records were reviewed to obtain data required for comparative assessments. RESULTS: The concentration (%ID/g) and biologic half-time of 131-Lym-1 in tumor were about twice those in normal tissues, although tumor half-time was similar to that of the thyroid. Pharmacokinetics were similar for patients in the MTD and LD trials, and for NHL and CLL patients in the LD trial, except that the latter group had less tumor concentration of 131I. Mean tumor radiation dose per unit of administered 131I was 1.0 Gy/GBq (3.7 rad/mCi) for patients with NHL whether in MTD or LD trials, about nine times greater than that for body or marrow. Tumor radiation dose was less and liver radiation dose was more in patients with CLL. Otherwise, radiation dosimetry was, on average, remarkably similar among groups of patients and among individual patients. Pharmacokinetics and dosimetry did not appear to be influenced by the amount of 131I or Lym-1 within the ranges administered. Tumor concentration of 131I and radiation dose per gigabecquerel were inversely related to tumor size but did not seem to be related to histologic grade or type, tumor burden or therapeutic response. CONCLUSION: The therapeutic index of 131I-Lym-1 was favorable, although the index for patients with CLL was less than that for patients with NHL. Pharmacokinetics and radiation dosimetry were, on average, remarkably similar among patients and groups of patients in different trials.     

Lung dosimetry for radioiodine treatment planning in the case of diffuse lung metastases.

The lungs are the most frequent sites of distant metastasis in differentiated thyroid carcinoma. Radioiodine treatment planning for these patients is usually performed following the Benua-Leeper method, which constrains the administered activity to 2.96 GBq (80 mCi) whole-body retention at 48 h after administration to prevent lung toxicity in the presence of iodine-avid lung metastases. This limit was derived from clinical experience, and a dosimetric analysis of lung and tumor absorbed dose would be useful to understand the implications of this limit on toxicity and tumor control. Because of highly nonuniform lung density and composition as well as the nonuniform activity distribution when the lungs contain tumor nodules, Monte Carlo dosimetry is required to estimate tumor and normal lung absorbed dose. Reassessment of this toxicity limit is also appropriate in light of the contemporary use of recombinant thyrotropin (thyroid-stimulating hormone) (rTSH) to prepare patients for radioiodine therapy. In this work we demonstrated the use of MCNP, a Monte Carlo electron and photon transport code, in a 3-dimensional (3D) imaging-based absorbed dose calculation for tumor and normal lungs. METHODS: A pediatric thyroid cancer patient with diffuse lung metastases was administered 37 MBq of (131)I after preparation with rTSH. SPECT/CT scans were performed over the chest at 27, 74, and 147 h after tracer administration. The time-activity curve for (131)I in the lungs was derived from the whole-body planar imaging and compared with that obtained from the quantitative SPECT methods. Reconstructed and coregistered SPECT/CT images were converted into 3D density and activity probability maps suitable for MCNP4b input. Absorbed dose maps were calculated using electron and photon transport in MCNP4b. Administered activity was estimated on the basis of the maximum tolerated dose (MTD) of 27.25 Gy to the normal lungs. Computational efficiency of the MCNP4b code was studied with a simple segmentation approach. In addition, the Benua-Leeper method was used to estimate the recommended administered activity. The standard dosing plan was modified to account for the weight of this pediatric patient, where the 2.96-GBq (80 mCi) whole-body retention was scaled to 2.44 GBq (66 mCi) to give the same dose rate of 43.6 rad/h in the lungs at 48 h. RESULTS: Using the MCNP4b code, both the spatial dose distribution and a dose-volume histogram were obtained for the lungs. An administered activity of 1.72 GBq (46.4 mCi) delivered the putative MTD of 27.25 Gy to the lungs with a tumor absorbed dose of 63.7 Gy. Directly applying the Benua-Leeper method, an administered activity of 3.89 GBq (105.0 mCi) was obtained, resulting in tumor and lung absorbed doses of 144.2 and 61.6 Gy, respectively, when the MCNP-based dosimetry was applied. The voxel-by-voxel calculation time of 4,642.3 h for photon transport was reduced to 16.8 h when the activity maps were segmented into 20 regions. CONCLUSION: MCNP4b-based, patient-specific 3D dosimetry is feasible and important in the dosimetry of thyroid cancer patients with avid lung metastases that exhibit prolonged retention in the lungs.     

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.     

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 ¹¹¹In-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 ¹¹¹In-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. Received 24 January and in revised form 20 March 2000     

PET scanning of iodine-124-3F9 as an approach to tumor dosimetry during treatment planning for radioimmunotherapy in a child with neuroblastoma.

A patient with advanced neuroblastoma who had failed chemotherapy presented with a large abdominal mass and virtually total bone marrow replacement by tumor on repeated marrow biopsies. She was considered a candidate for a Phase I 131I-3F8 radioimmunotherapy trial, (MSKCC 89-141A). As a potential aid to treatment planning, a test dose of 124I-3F8 was injected and the patient was imaged over the 72 hr postinjection using two BGO based PET scanners of different designs. Time activity curves were obtained, and the cumulated activity concentration of radiolabeled 3F8 in tumor was determined. Based on MIRD, an estimated radiation absorbed dose for 131I-3F8 was 7.55 rad/mCi, in the most antibody avid lesions. Because of low uptake and unfavorable dosimetry in some bulky tumor sites, it was decided not to treat the patient with radiolabeled antibody. Positron emission tomography of 124I-labeled antibodies can be used to measure cumulated activity or residence time in tumor for more accurate estimates of radiation absorbed tumor dose from radioiodinated antibodies and can help guide management decisions in patients who are candidates for radioimmunotherapy.     

Phase I therapy study of 186Re-labeled chimeric monoclonal antibody U36 in patients with squamous cell carcinoma of the head and neck.

A phase I therapy study was conducted to determine the safety, maximum tolerated dose (MTD), pharmacokinetics, dosimetry, immunogenicity, and therapeutic potential of 186Re-labeled anti-CD44v6 chimeric monoclonal antibody (cMAb) U36 in patients with squamous cell carcinoma of the head and neck (HNSCC). The potential of a diagnostic study with 99mTc-cMAb U36 to predict the biodistribution of 186Re-cMAb U36 was evaluated. METHODS: Thirteen patients with recurrent or metastatic HNSCC were given 750 MBq 99mTc-cMAb U36 (2 mg) followed 1 wk later by a single dose of 186Re-cMAb U36 (12 or 52 mg) in radiation dose-escalating steps of 0.4, 1.0, and 1.5 GBq/m2. After each administration, planar and SPECT images were obtained, and the pharmacokinetics and development of human antimurine as well as anti-cMAb responses were determined. Radiation absorbed doses to tumor, red marrow, and organs were calculated. RESULTS: Administration was well tolerated, and excellent targeting of tumor lesions was seen in all patients. Dose-limiting myelotoxicity (thrombocytopenia being most prominent) was the only toxicity observed, resulting in grade 4 myelotoxicity in 2 patients treated with 1.5 GBq/m2. The MTD was established at 1.0 GBq/m2, at which a transient grade 3 thrombocytopenia was seen in 1 patient. One patient showed stable disease for 6 mo after treatment at the MTD. The 2 patients with dose-limiting myelotoxicity showed a marked reduction in tumor size. The reduction was of short duration and, therefore, not considered an objective response. Tumor absorbed doses at MTD ranged from 3.0 to 18.1 Gy. Red marrow doses ranged from 20 to 112 cGy (mean, 51 +/- 16 cGy/GBq) and correlated with platelet nadir (r = 0.8; P < 0.01). Pharmacokinetics varied between patients treated at the same dose level and were accurately predicted by the diagnostic procedure. Five patients experienced a human anti-cMAb response, 1 of which was a human antimouse antibody response. CONCLUSION: This study shows that 186Re-cMAb U36 can be safely administered, with dose-limiting myelotoxicity at 41 mCi/m2. The use of cMAb U36 instead of its murine counterpart did not decrease the induction of human antibody responses. The availability of a 99mTc-labeled diagnostic study that can predict the pharmacokinetics of 186Re-cMAb U36 offers the possibility of using such a study for selection of a safe radioimmunotherapy dose.     

^131I-美妥昔单抗联合动脉内化疗栓塞治疗原发性肝癌的内照射吸收剂量估算

目的对^131I-美妥昔单克隆抗体（简称单抗）联合动脉内化疗栓塞（TACE）治疗原发性肝癌患者器官的内照射吸收剂量进行估算。方法21例患者肝动脉内按体质量注入^131I-美妥昔单抗（27．75MBq／kg）和混合化疗药物的碘化油乳剂。用1计数仪测量5min和0．5,2,4,24,48,72,120,168h血样和尿样的放射性。用SPECT仪行4或5次全身扫描。用感兴趣区图像处理法计算主要器官和全身放射性活度占给予放射性活度的百分数（％ID）,SPSS12．0软件拟合时间-％ID曲线,计算累积活度,依据医学内照射辐射剂量学（MIRD）方法和血液间接法计算器官和红骨髓的内照射吸收剂量,计算肿瘤／非肿瘤放射性比值。结果^131I-美妥昔单抗的平均剂量为1．89（1．47～223）GBq／次。显像示放射性主要浓聚于肝区肿瘤组织,随时间延长,甲状腺后期有放射性浓聚,体内其他组织未见明显放射性分布。器官吸收剂量（12例）：肝（3．19±1．01）Gy,脾（3．65±2．41）Gy,甲状腺（3．61±2．40）Gy,肺（0．97±0．23）Gy,肾（0．96±0．35）Gy,全身（0．57±1．55）Gy,红骨髓（0．55±0．09）Gy（7例）。肿瘤／肝放射陛比值（7例）：3h为2．88±1．11,64h为2．15±0．53,120h为1．81±0．39,168h为1．64±0．39。结论依据MIRD方法计算获得了主要器官、红骨髓和全身内照射吸收剂量,这对更好评价疗效、不良反应和制订个体化方案有重要意义。     

Empiric radioactive iodine dosing regimens frequently exceed maximum tolerated activity levels in elderly patients with thyroid cancer.

Although 131I-iodine (RAI) therapy is a mainstay in the treatment of metastatic thyroid cancer, there is controversy regarding the maximum activity that can safely be administered without dosimetric determination of the maximum tolerable activity (MTA). At most institutions, a fixed empiric dosing strategy is often used, with administered activities ranging from 5.55 to 9.25 GBq (150-250 mCi). In our experience with dosimetry, we have observed that this empiric dosing strategy often results in administered RAI activities exceeding the MTA safety limit of 200 cGy (rads) to the blood or bone marrow in many patients with metastatic thyroid cancer. METHODS: We retrospectively analyzed 535 hypothyroid dosimetry studies performed as part of routine clinical care in 328 patients with apparently normal renal function. RESULTS: The MTA was less than 5.18 GBq (140 mCi) in 3%, less than 7.4 GBq (200 mCi) in 8%, and less than 9.25 GBq (250 mCi) in 19%. Analysis of MTA values by age at the time of dosimetry revealed little change in the MTA until the age of 70 y, when a significant decrease occurred. An empiric administered activity of 7.4 GBq (200 mCi) would exceed the MTA in 8%-15% of patients less than 70 y old and 22%-38% of patients 70 y old or older. However, administration of 9.25 GBq (250 mCi) would exceed the MTA in 22% of patients less than 70 y old and 50% of patients 70 y old or older. Factors associated with a lowering of MTA to less than 9.25 GBq (250 mCi) were age at dosimetry greater than 45 y, the female sex, subtotal thyroidectomy, and RAI-avid diffuse bilateral pulmonary metastases. CONCLUSION: Administered RAI activities of less than 5.18 GBq (140 mCi) rarely exposed blood to more than 200 cGy except in the very elderly. However, administered activities of 7.4-9.25 GBq (200-250 mCi) frequently exceeded the calculated MTA in patients 70 y old or older. Therefore, dosimetry-guided RAI therapy may be preferable to fixed-dose RAI treatment strategies in older patients with thyroid cancer and in patients with RAI-avid diffuse bilateral pulmonary metastases, even when renal function is normal.     

Radioisotope therapy of malignant pheochromocytoma with iodine-131 metaiodobenzylguanidine--absorbed dose assessments using SPECT]

The correlation of absorbed doses D (rad) of tumors in 4 patients with malignant pheochromocytoma, who were treated by 131I-MIBG (3.7 GBq), with their clinical courses were analyzed and the clinical significance of determination of absorbed dose was discussed. Absorbed doses of 131I-MIBG in the tumors were measured by using SPECT at the time of therapy. Absorbed dose was calculated based on the MIRD (medical internal radiation dose committee) equation. Tumor volumes were ranged from 17 g-100 g (mean 40 g), effective half lives were ranged from 1.3 days-5.9 days (mean 3.6 days), and tumor absorbed doses were varied between 5.4 Gy-68 Gy (mean 40 Gy). When the absorbed doses of the tumor exceeded over 40 Gy, good clinical responses were obtained. The initial treatment seemed to be important for 131I-MIBG therapy, since the absorbed doses in the following therapy became reduced. These results indicate that the quantitative SPECT for radioisotope therapy is clinically valid and that the calculated absorbed doses correlate well with clinical responses.     

Preliminary results of transarterial rhenium-188 HDD lipiodol in the treatment of inoperable primary hepatocellular carcinoma

A multicentre study was sponsored by the International Atomic Energy Agency (Vienna) to assess the safety and efficacy of trans-arterial rhenium-188 HDD conjugated lipiodol (radioconjugate) in the treatment of patients with inoperable hepatocellular carcinoma (HCC). The radioconjugate was prepared by using an HDD (4-hexadecyl 1-2,9,9-tetramethyl-4,7-diaza-1,10-decanethiol) kit developed in Korea, and lipiodol. Over a period of 18 months, 70 patients received at least one treatment of radioconjugate. Some patients were re-treated if there was no evidence of disease progression. The level of radioconjugate administered was based on radiation-absorbed dose to critical normal organs, calculated following a scout dose of radioconjugate. The organs at greatest risk for radiation toxicity are the normal liver, the lung and the bone marrow. An Excel spreadsheet was used to determine maximum tolerated activity (MTA), defined as the amount of radioactivity calculated to deliver no more than 12 Gy to lungs, or 30 Gy to liver, or 1.5 Gy to bone marrow. These doses have been found to be safe in multiple trials using external beam therapy, but this has not been confirmed for systemically administered radiopharmaceuticals. Patients were followed for at least 12 weeks after therapy, until recovery from all toxicity. The clinical parameters evaluated included toxicity, response as determined by contrast-enhanced computed tomography, palliation of symptoms, overall survival, performance status (Karnofsky) and hepatic function (Childs classification). Liver function tests, serum -fetoprotein (AFP) levels and complete blood counts were done at each follow-up visit. In the majority of patients, the scout dose studies indicated the radiation absorbed dose to normal liver to be the limiting factor to the treatment dose, while in a few patients dose to lung was the limiting factor. Radiation dose to bone marrow was negligible and was thus not a factor for the MTA calculations. Side-effects were minimal and usually presented as loss of appetite, right hypochondrial discomfort and low-grade fever, even at high levels of administered radioactivity. The symptoms resolved with simple supportive therapy within 3 days of onset. Liver function tests at 24 and 72 h showed no significant changes and complete blood counts at 1 week, 4 weeks and 12 weeks showed no changes (no bone marrow suppression). Sixteen patients were treated in the dose escalation phase of the study, when the activities administered started at 1.8 GBq (50 mCi) and rose to 7.7 GBq (206 mCi). In the efficacy phase of the study a further 54 patients were treated. Both groups of patients are included in this paper. The treatment activity of ¹⁸⁸Re-lipiodol administered transarterially ranged from 1.8 to 9.8 GBq (50–265 mCi), with a mean activity of 4.6 GBq (124 mCi). Survival at 3 months was 90%, and at 6 months, 60%; 19% survived for 1 year. Mean survival after treatment in the total treated group of 70 patients was 9.5 months, with a range of 1–18 months. The results of this multicentre study show that ¹⁸⁸Re-lipiodol is a safe and cost-effective method to treat primary HCC via the transarterial route. In terms of efficacy, it is potentially a new therapeutic approach for further evaluation by treatment of larger numbers of patients.     

Patient biodistribution of intraperitoneally administered yttrium-90-labeled antibody

Although 90Y is one of the best radionuclides for radioimmunotherapeutic applications, the lack of gamma rays in its decay complicates the estimation of radiation dose since its biodistribution cannot be accurately determined by external imaging. A limited clinical trial has been conducted with tracer doses (1 mCi) of 90Y in five patients who then received second-look surgery such that tissue samples were obtained for accurate radioactivity quantitation by in vitro counting. The anti-ovarian antibody OC-125 as the F(ab')2 fragment was coupled with diethylenetriaminepentaacetic acid, radiolabeled with 90Y and administered intraperitoneally to patients with suspected or documented ovarian cancer. Size exclusion and ion exchange high performance liquid chromatography analysis of patient ascitic fluid and serum samples showed no evidence of radiolabel instability although a high molecular weight species (presumably immune complex) was observed in three patients. Total urinary excretion of radioactivity prior to surgery averaged 7% of the administered radioactivity while at surgery the mean organ accumulation was 8% of the administered radioactivity in serum, 10% in liver, 7% in bone marrow, and 19% in bone with large patient to patient variation. The mean tumor/normal tissue radioactivity ratio varied between 3 and 25. On the assumption that the above radioactivity levels were achieved immediately following administration, that the radioactivity remained in situ until decayed and that the dimensions of tumor were sufficient to completely attenuate the emissions of 90Y, the dose to tumor for a 1-mCi administration would be approximately 50 rad with normal tissues receiving approximately 8 rad.     

Dosimetry and toxicity of Quadramet for bone marrow ablation in multiple myeloma and other haematological malignancies

Standard treatment regimens for haematological malignancies include myeloablative chemoradiotherapy and subsequent rescue by stem cell transplantation. However, these treatment regimens have significant associated mortality and morbidity, and disease recurrence remains a problem. One alternative approach is the targeted delivery of radiotherapy to the marrow using a bone-seeking agent labelled with an appropriate radioisotope, with the aim of delivering a potentially ablative radiation dose to marrow while minimising non-haematological toxicity. Pharmacokinetics and radiation dosimetry for a commercial preparation of samarium-153 ethylene diamine tetramethylene phosphonate (EDTMP; Quadramet) were evaluated in 43 tracer (average dose 740 MBq) studies of 42 patients with haematological malignancies. Measurements of 24-h retention were also available following infusion of 18-48 GBq in 15 patients. Quadramet cleared rapidly from the tissue, with a median biological half-life of 1.4 h. Activity taken up by the skeleton was firmly bound, with activity decreasing according to physical half-life at 24 h in 29 of the 43 cases. The percentage activity retained in the skeleton at 24 h with tracer doses was high (62%+/-13%), although this decreased to approximately 30% with therapy infusions. Because of this decrease in retention, the maximum feasible therapy activity for this formulation of Quadramet is 35 GBq. Median absorbed marrow radiation dose was 0.78 Gy/GBq in tracer studies: the decreased retention at high activities means that this corresponds to a median dose of 12 Gy for 35 GBq administered activity. It is possible to use 24-h retention as a rough guide to marrow dose in individual patients. In tracer studies, median bladder radiation dose was 0.22 Gy/GBq and radiation dose to the liver was very conservatively estimated at 0.2 Gy/GBq. After therapy infusions of up to 50 GBq in 37 patients, non-haematopoietic toxicity was not seen in any patient. In addition, myelosuppression was achieved without evidence of myelofibrosis. The residual dose rate to marrow fell to a level acceptable for stem cell re-infusion by 2 weeks after administration.     

Initial results for Hybrid SPECT--conjugate-view tumor dosimetry in 131I-anti-B1 antibody therapy of previously untreated patients with lymphoma.

A study of the use of 131I-labeled anti-B1 monoclonal antibody, proceeded by an unlabeled predose, for therapy of previously untreated non-Hodgkin's lymphoma patients has recently been completed at the University of Michigan, Ann Arbor. More than half of the patients treated were imaged intratherapy with SPECT to separate apparently large tumors, unresolved by conjugate views, into individual ones specified by CT scan. The dosimetry of these tumors is reported here. METHODS: The activity-quantification procedure used 3-dimensional CT-to-SPECT fusion so that attenuation maps could be computed from CT and that volumes of interest could be drawn on the CT slices and transferred to the SPECT images. Daily conjugate-view images after a tracer dose of labeled anti-B1 antibody followed by an unlabeled predose provided the shape of the time-activity curve for the calculation of therapy dosimetry. Reconstructed SPECT counts that were within a volume of interest were converted to activity by using a background-and-radius-adaptive conversion factor. Activities were increased for tumors less than 200 g using a recovery-coefficient factor derived from activity measurements for a set of spheres with volumes ranging from 1.6 to 200 cm3. The calculated tumor radiation absorbed dose was based, in part, on the CT volume and on the intratherapy-SPECT activity. RESULTS: The mean of the radiation dose values for 131 abdominal or pelvic tumors in 31 patients was 616 cGy with a standard deviation of +/- 50 cGy. The largest dose was 40 Gy and the smallest dose was 73 cGy. The mean volume for the tumors was 59.2 +/- 11.2 cm3. The correlation coefficient between absorbed dose and tumor volume was small (r2 = 0.007), and the slope of the least-squares fit represented a decrease of only 36.4 cGy per 100 cm3 increase in volume. This small slope may reflect a characteristic of anti-B1 antibody therapy that is important for its success. The mean absorbed dose per unit administered activity was 1.83 +/- 0.145 Gy/GBq. The largest value was 12.6 Gy/GBq, and the smallest value was 0.149 Gy/GBq. The mean dose for 9 axillary tumors in 5 patients was significantly lower than the average dose for abdominal and pelvic tumors (P = 0.01). Therefore, axillary tumors should be grouped separately in assessing dose-response relationships. Anecdotal patient results tended to verify the validity of using the shape of the conjugate-view time-activity curve for the average SPECT-intratherapy curve. However, there was also an indication that the shape varies somewhat for individual tumors with respect to time to peak. CONCLUSION: Hybrid SPECT-conjugate-view dosimetry provided radiation absorbed dose estimates for the individual patient tumors that were resolved by CT.     

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-guided radioactive iodine treatment in patients with metastatic differentiated thyroid cancer: largest safe dose using a risk-adapted approach.

This study is a retrospective analysis of 124 differentiated thyroid cancer patients who underwent dosimetric evaluation using MIRD methodology over a period of 15 y. The objectives of the study were to demonstrate the clinical use of dosimetry-guided radioactive iodine ([RAI] (131)I) treatment and the safe and effective application of a 3-Gy bone marrow (BM) dose in patients with differentiated thyroid cancer. METHODS: Tumor and BM dose estimates were obtained. The administered activity that would deliver a maximum safe dose to the organ at risk (red BM or lungs) was determined as well as the resulting doses to the metastases. The clinical benefit of an individual RAI treatment was predicted on the basis of the dose estimates and the expected therapeutic response. Each patient's response to treatment was assessed clinically and by monitoring the hematologic profile. RESULTS: One hundred twenty-four patients underwent 187 dosimetric evaluations. One hundred four RAI treatments were performed. A complete response at metastatic deposits was attained with absorbed doses of >100 Gy. No permanent BM suppression was observed in patients who received absorbed doses of <3 Gy to BM. The maximum administered dose was 38.5 GBq (1,040 mCi) with the BM dose limitation. CONCLUSION: Dosimetry-guided RAI treatment allows administration of the maximum possible RAI dose to achieve the maximum therapeutic benefit. Estimation of tumor dose rates helps to determine the curative versus the palliative intent of the therapy.     

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.     

Relationship between cumulative radiation dose and salivary gland uptake associated with radioiodine therapy of thyroid cancer

AIM: To estimate the individual absorbed dose to the parotid and submandibular salivary glands in radioiodine therapy and its dependence from the previous cumulative therapy. METHODS: Fifty-five patients with differentiated thyroid carcinoma after thyroidectomy received 1-21 GBq (131)I using single activities of 1-6 GBq. The patients were stratified according to the cumulative activities into low-activity (1-2 GBq), middle-activity (3-7 GBq), and high-activity groups (9-21 GBq). The time-activity curves over the respective salivary glands were derived from multiple static calibrated images measured for each patient up to 48 h after ingestion of the radioiodine therapy capsule with a gamma camera. Manually drawn regions of interests were used to determine the background activities and the activities arising from the salivary glands. The gland volumes were determined by ultrasonography using appropriate volume models. RESULTS: The median absorbed dose per administered activity of each single parotid and submandibular gland was about 0.15 Gy.GBq (range, 0.1-0.3 Gy.GBq(-1)) and 0.48 Gy.GBq(-1) (range, 0.2-1.2 Gy.GBq(-1)), respectively. The maximum uptake of both gland types was significantly lower for the high-activity than for the low-activity groups and correlated with the mean cumulative administered activity of the activity groups. CONCLUSION: The iodine uptake of salivary glands is significantly reduced, whereas the absorbed dose per administered (131)I activity was not significantly decreased during the course of therapy. Comparing the well-known dose-effect relationships in external radiation therapy, the absorbed dose per administered (131)I activity is too low to induce comparable radiation damage, suggesting an inhomogeneous distribution of (131)I in human salivary glands.     

Re-186 HEDP conditioning therapy in patients with advanced acute lymphoblastic leukemia before allogeneic bone marrow transplantation

The authors present their experience with dose calculation of Retin1,1-hydroxyethylidene-186-diphosphonate (Re-186 HEDP) therapy used as part of an intensified conditioning regimen before allogeneic stem cell transplantation in 2 patients with advanced acute lymphoblastic leukemia during the second partial or third complete remission. Kidneys were shielded during total-body irradiation (TBI) to limit the TBI-mediated renal radiation dose to 7 Gy. The aim of this dose calculation of Re-186 HEDP therapy was to deliver additional radiotherapy to the red bone marrow without exposing more than an additional 5 Gy to the kidneys in addition to the TBI standard dose of 12.6 Gy. Pretherapeutic kidney scintigraphy (Tc-99m mercaptoacetyltriglycine) showed normal results. Thus, dynamic Tc-99m methylene diphosphonate bone scintigraphy was used to calculate the expected bone marrow and kidney doses. A total amount of 8.8 GBq (238 mCi) Re-186 HEDP was given to patient no. 1 and 14.3 GBq (387 mCi) Re-186 HEDP was given to patient no. 2. Re-186 HEDP activity was monitored based on its gamma radiation measurement daily for 5 days in patient no. 1 and 7 days in patient no. 2. Therapeutic Re-186 isotope distribution and biologic half-life correlated well with the prediction by a pretherapeutic Tc-99m methylene diphosphonate scan. The calculated effective Re-186 bone marrow dose was 3.3 Gy for patient no. 1 and 5.6 Gy for patient no. 2. Effective kidney doses were 1.6 Gy and 2.1 Gy respectively. No unexpected complications occurred after completing conditioning and allogeneic stem cell transplantation. Posttransplant kidney function remained normal. Patient no. 1 remains in a second complete remission of his advanced acute lymphoblastic leukemia 18 months after HEDP therapy. Patient no. 2 relapsed 5 months after transplantation and eventually died as a result of progressive disease. The authors conclude that Re-186 HEDP will be able to increase the total additional bone marrow dose. In patients in whom the kidney dose is limited to 5 Gy in addition to TBI, doses near 10 Gy can be achieved on the bone marrow.     

Lung toxicity in radioiodine therapy of thyroid carcinoma: development of a dose-rate method and dosimetric implications of the 80-mCi rule.

Based on an extensive dataset analyzed by Benua et al., a whole-body retention threshold of 2.96 GBq (80 mCi) at 48 h has been used to limit the radioactivity of (131)I administered to thyroid cancer patients with diffuse pulmonary metastases. In this work, the 80-mCi activity retention limit is used to derive lung-absorbed doses and dose rates. The resulting dose-rate-based limits make it possible to account for patient-specific differences in lung geometry. This is particularly important, for example, in pediatric patients exhibiting diffuse lung metastases. The approach also highlights the impact of altered radioiodine kinetics as seen with recombinant human thyroid-stimulating hormone. METHODS: The dose-rate constraint (DRC) was defined as the absorbed dose rate to the lungs of the adult female reference phantom when 80 mCi of (131)I are in the body and 90% of this is uniformly distributed in the lungs. With this definition, the 80-mCi rule was generalized by calculating the activity required to yield a dose rate equal to DRC using lung-to-lung S factor values corresponding to different reference phantoms. RESULTS: A DRC value of 43.6 cGy/h was obtained. Applying this DRC to the adult male phantom and to the phantom of a 15-y-old yields equivalent 48-h activity limits of 3.72 GBq (101 mCi) and 2.45 GBq (66.2 mCi), respectively. Depending on model parameters, the absorbed doses to lungs ranged from 57 to 112 Gy; the photon-only portion, which better reflects the dose to normal lung parenchyma, ranged from 4.9 to 55 Gy. CONCLUSION: A dose-rate-based version of the 80-mCi rule is derived and used to demonstrate application of this rule to pediatric patients and to adult male patients. The implications of the 80-mCi rule are also examined. The assumption of uniform energy deposition in the lungs leads to substantially overestimated absorbed doses. Severe radiation-induced lung toxicity, expected at normal lung absorbed doses of 25-27 Gy, is avoided, probably because most of the local electron dose is delivered to tumor tissue instead of to normal lung parenchyma. The possibility of using a DRC to adjust treatment for different clinical situations is illustrated. The analysis suggests that a dosimetry-based approach will be particularly important in the treatment of patients with lung metastases when a recombinant human thyroid-stimulating hormone protocol is used.     

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.