MIRD pamphlet No. 20: the effect of model assumptions on kidney dosimetry and response--implications for radionuclide therapy.

UNLABELLED: Renal toxicity associated with small-molecule radionuclide therapy has been shown to be dose-limiting for many clinical studies. Strategies for maximizing dose to the target tissues while sparing normal critical organs based on absorbed dose and biologic response parameters are commonly used in external-beam therapy. However, radiopharmaceuticals passing though the kidneys result in a differential dose rate to suborgan elements, presenting a significant challenge in assessing an accurate dose-response relationship that is predictive of toxicity in future patients. We have modeled the multiregional internal dosimetry of the kidneys combined with the biologic response parameters based on experience with brachytherapy and external-beam radiation therapy to provide an approach for predicting radiation toxicity to the kidneys. METHODS: The multiregion kidney dosimetry model of MIRD pamphlet no. 19 has been used to calculate absorbed dose to regional structures based on preclinical and clinical data. Using the linear quadratic model for radiobiologic response, we computed regionally based surviving fractions for the kidney cortex and medulla in terms of their concentration ratios for several examples of radiopharmaceutical uptake and clearance. We used past experience to illustrate the relationship between absorbed dose and calculated biologically effective dose (BED) with radionuclide-induced nephrotoxicity. RESULTS: Parametric analysis for the examples showed that high dose rates associated with regions of high activity concentration resulted in the greatest decrease in tissue survival. Higher dose rates from short-lived radionuclides or increased localization of radiopharmaceuticals in radiosensitive kidney subregions can potentially lead to greater whole-organ toxicity. This finding is consistent with reports of kidney toxicity associated with early peptide receptor radionuclide therapy and (166)Ho-phosphonate clinical investigations. CONCLUSION: Radionuclide therapy dose-response data, when expressed in terms of biologically effective dose, have been found to be consistent with external-beam experience for predicting kidney toxicity. Model predictions using both the multiregion kidney and linear quadratic models may serve to guide the investigator in planning and optimizing future clinical trials of radionuclide therapy.

166Ho-DOTMP radiation-absorbed dose estimation for skeletal targeted radiotherapy.

UNLABELLED: 166Ho-1,4,7,10-tetraazacyclododecane-1,4,7,10-tetramethylene-phosphonate (DOTMP) is a tetraphosphonate molecule radiolabeled with 166Ho that localizes to bone surfaces. This study evaluated pharmacokinetics and radiation-absorbed dose to all organs from this beta-emitting radiopharmaceutical. METHODS: After two 1.1-GBq administrations of 166Ho-DOTMP, data from whole-body counting using a gamma-camera or uptake probe were assessed for reproducibility of whole-body retention in 12 patients with multiple myeloma. The radiation-absorbed dose to normal organs was estimated using MIRD methodology, applying residence times and S values for 166Ho. Marrow dose was estimated from measured activity retained after 18 h. The activity to deliver a therapeutic dose of 25 Gy to the marrow was determined. Methods based on region-of-interest (ROI) and whole-body clearance were evaluated to estimate kidney activity, because the radiotracer is rapidly excreted in the urine. The dose to the surface of the bladder wall was estimated using a dynamic bladder model. RESULTS: In clinical practice, gamma-camera methods were more reliable than uptake probe-based methods for whole-body counting. The intrapatient variability of dose calculations was less than 10% between the 2 tracer studies. Skeletal uptake of 166Ho-DOTMP varied from 19% to 39% (mean, 28%). The activity of 166Ho prescribed for therapy ranged from 38 to 67 GBq (1,030-1,810 mCi). After high-dose therapy, the estimates of absorbed dose to the kidney varied from 1.6 to 4 Gy using the whole-body clearance-based method and from 8.3 to 17.3 Gy using the ROI-based method. Bladder dose ranged from 10 to 20 Gy, bone surface dose ranged from 39 to 57 Gy, and doses to other organs were less than 2 Gy for all patients. Repetitive administration had no impact on tracer biodistribution, pharmacokinetics, or organ dose. CONCLUSION: Pharmacokinetics analysis validated gamma-camera whole-body counting of 166Ho as an appropriate approach to assess clearance and to estimate radiation-absorbed dose to normal organs except the kidneys. Quantitative gamma-camera imaging is difficult and requires scatter subtraction because of the multiple energy emissions of 166Ho. Kidney dose estimates were approximately 5-fold higher when the ROI-based method was used rather than the clearance-based model, and neither appeared reliable. In future clinical trials with 166Ho-DOTMP, we recommend that dose estimation based on the methods described here be used for all organs except the kidneys. Assumptions for the kidney dose require further evaluation.

Patient-specific dosimetry of pretargeted radioimmunotherapy using CC49 fusion protein in patients with gastrointestinal malignancies.

UNLABELLED: Pretargeted radioimmunotherapy (RIT) using CC49 fusion protein, comprised of CC49-(scFv)4 and streptavidin, in conjunction with 90Y/111In-DOTA-biotin (DOTA = dodecanetetraacetic acid) provides a new opportunity to improve efficacy by increasing the tumor-to-normal tissue dose ratio. To our knowledge, the patient-specific dosimetry of pretargeted 90Y/111In-DOTA-biotin after CC49 fusion protein in patients has not been reported previously. METHODS: Nine patients received 3-step pretargeted RIT: (a) 160 mg/m2 of CC49 fusion protein, (b) synthetic clearing agent (sCA) at 48 or 72 h later, and (c) 90Y/111In-DOTA-biotin 24 h after the sCA administration. Sequential whole-body 111In images were acquired immediately and at 2-144 h after injection of 90Y/111In-DOTA-biotin. Geometric-mean quantification with background and attenuation correction was used for liver and lung dosimetry. Effective point source quantification was used for spleen, kidneys, and tumors. Organ and tumor 90Y doses were calculated based on 111In imaging data and the MIRD formalism using patient-specific organ masses determined from CT images. Patient-specific marrow doses were determined based on radioactivity concentration in the blood. RESULTS: The 90Y/111In-DOTA-biotin had a rapid plasma clearance, which was biphasic with <10% residual at 8 h. Organ masses ranged from 1,263 to 3,855 g for liver, 95 to 1,009 g for spleen, and 309 to 578 g for kidneys. The patient-specific mean 90Y dose (cGy/37 MBq, or rad/mCi) was 0.53 (0.32-0.78) to whole body, 3.75 (0.63-6.89) to liver, 2.32 (0.58-4.46) to spleen, 7.02 (3.36-11.2) to kidneys, 0.30 (0.09-0.44) to lungs, 0.22 (0.12-0.34) to marrow, and 28.9 (4.18-121.6) to tumors. CONCLUSION: Radiation dose to normal organs from circulating radionuclide is substantially reduced using pretargeted RIT. Tumor-to-normal organ dose ratios were increased about 8- to 11-fold compared with reported patient-specific mean dose to liver, spleen, marrow, and tumors from 90Y-CC49.

Testicular uptake and radiation dose in patients receiving Zevalin and Pretarget CC49Fusion protein.

OBJECTIVE: Radiation dose to the testes from radionuclide therapies is of concern. This study evaluated image-quantification methods for testicular uptake in a phantom and in patients. METHODS: A 50-mL vial and a large water tank were used to simulate testes and the body, respectively. Activity concentration in the vial and water tank was prepared to generate testes-to-background concentrations of 1.3 and 1.1. Five male lymphoma patients who received a Zevalin (Biogen Idec, Cambridge, MA) regimen and 6 male colorectal cancer patients who received a Pretarget (Neo Rx, Seattle, WA) CC49Fusion protein were evaluated. Testicular activity was quantified using two methods: (1) geometric-mean, background-corrected testicular region of interest (ROI) counts as a fraction of body counts without explicit attenuation correction (Zevalin Kit); (2) background-corrected anterior testicular ROI counts with attenuation correction using known depth in the phantom and CT depth in patients. RESULTS: In the phantom study, Method 1 underestimated 49% and 39%, at image contrast of 1.3 and 1.1, respectively. Quantification was improved using Method 2 (7% for a 1.3 contrast, -17% for a 1.1 contrast). Method 2 was used in patients because background-corrected posterior ROI counts were statistically unreliable due to poor image contrast. In patients receiving Zevalin, the median peak percent injected dose (%ID)/testis was 0.10 (range, 0.08-0.18) with a median biologic half-time (T(bio1/2)) of 156 (range, 91-4200) hours. The median dose was 2.4 (range, 1.5-3.6) Gy/GBq, compared to the originally reported mean dose of 9.1 (range, 5.4-11.4) Gy/GBq (Zevalin package insert). In patients receiving the Pretarget CC49Fusion protein, the median peak %ID/testis was 0.22 (range, 0.05-0.29) with a median T(bio1/2) of 44 (range, 37-64) hours. The median dose was 0.84 (range, 0.3-1.2) Gy/GBq. CONCLUSION: This study found that testicular doses from Zevalin were much lower than that originally reported in the package insert. The median testicular dose from Pretarget CC49Fusion protein was less than half that of the median testicular dose from Zevalin.

Pretargeted radioimmunotherapy (RIT) with a novel anti-TAG-72 fusion protein.

Pretargeted radioimmunotherapy (RIT) increases the dose of radionuclide delivered to tumor sites while limiting radiation to normal tissues. The three components in Pretarget include a streptavidin-containing targeting molecule, a synthetic clearing agent (sCA), and (90)Y and/or (111)In-DOTA-biotin. This trial determined the feasibility and safety of using a genetically engineered fusion protein directed to TAG-72 as the targeting agent. Nine (9) patients with metastatic colorectal cancer (TAG-72+) received 160 mg/m(2) of CC49Fusion protein intravenously (i.v.), followed by the sCA, 45 mg/m(2) i.v. Twenty-four (24) hours later, patients received radiolabeled DOTA-biotin (either 0.65 or 1.3 mg/m(2)). All patients received 5 mCi of (111)In-DOTA-biotin for imaging and dosimetry purposes and patients 4-9 received 10 mCi/m2 of (90)Y-DOTA-biotin as well. The mean plasma T1/2 of CC49Fusion protein was 23 +/- 6 hours. Greater than 95% of the circulating CC49Fusion protein was eliminated from the circulation within 6 hours of sCA administration. The radiolabeled DOTA-biotin rapidly localized to tumor sites while the unbound fraction was rapidly excreted. The mean tumor-to-marrow radiation dose ratio was 139:1 and mean tumor: whole body was 56:1. No infusion-related, renal, hepatic, or hematologic toxicities were noted. CC49Fusion protein performs well in a pretargeted RIT schema, and further study with escalating doses of (90)Y should be pursued. This strategy has the potential to deliver effective radiation tumor doses to TAG- 72+ tumors.

Bone marrow dosimetry using blood-based models for radiolabeled antibody therapy: a multiinstitutional comparison.

UNLABELLED: Standardization of marrow dosimetry is of considerable importance when estimating dose-response for a multicentered clinical trial involving radionuclide therapy. However, it is only within the past five years that the intercomparison of marrow dosimetry results among separate clinical trials that use the same agent has become scientifically feasible. In this work, we have analyzed reported marrow dosimetry results from radioimmunotherapy trials and recalculated marrow absorbed doses at a central facility using a standard blood model with patient-specific source data. The basic approach used in the American Association of Physicists in Medicine (AAPM)/Sgouros marrow dosimetry methodology was common to calculation performed at all participating institutions, including the central facility. Differences in dose estimates associated with starting assumptions and the exact implementation of the AAPM/Sgouros calculation methodology used by the source institutions and the central facility were quantified and compared. METHODS: Data from 22 patients enrolled in radiolabeled antibody clinical trials were randomly selected from 7 participating institutions for the assessment of marrow dose. The analysis was restricted to those patients who were treated with 131I- or 186Re-labeled antibody and had no marrow involvement. Calculation of bone marrow dose at each participating institution was unique to the trial or institution, but all used some form of the AAPM/Sgouros blood model approach. The central facility adopted a marrow dosimetry model based on the AAPM/Sgouros model for radiolabeled antibodies using the standard MIRD approach to the remainder-of-body contribution. A standardized approach to account for variations in patient mass was used for the remainder-of-body component. To simplify clinical implementation, regional marrow uptake and time-dependent changes in the marrow-to-blood concentration ratio were not included. Methods of formatting the collection of standard datasets useful in defining dose-response parameters are also presented. RESULTS: Bone marrow doses were calculated according to the method described for each of the 22 patients based on the patient-specific data supplied by the participating institutions. These values were then individually compared with the marrow doses originally reported by each institution. Comparison of the two calculation methods was expressed as a ratio of the marrow doses for each patient. The mean ratio for the dose estimates at the participating institution calculation compared with the central laboratory value was 0.920 +/- 0.259 (mean +/- SD), with a range from 0.708 to 1.202. CONCLUSION: The independent use of the AAPM/Sgouros method blood model approach to marrow dosimetry has brought these dose estimates to within 30% of the results obtained centrally compared with substantially higher uncertainties reported previously. Variations in calculation methodology or initial assumptions adopted by individual institutions may still contribute significant uncertainty to dose estimates, even when the same data are used as a starting point for the calculation comparison shown here. A clinically relevant, standard method for marrow dosimetry for radiolabeled antibodies is proposed as a benchmark for intercomparison purposes. A parameter sensitivity analysis and a summary discussion of the use of this model for potentially improving dose-response data correlation are also presented.

Clinical aspects of radiation nephropathy.

Small radiolabeled molecules are finding increasing clinical use for targeted radionuclide therapy. With the administration of radiolabeled small molecules, the bone marrow is not necessarily the first organ to show radiation toxicity. Rapid excretion of radioactivity through the urinary tract and the retention of radiolabeled small-protein molecules in the kidneys may expose the kidneys to radiation sufficient enough to cause toxicity--and in clinical trials, radiation toxicity of the urinary tract has become clinically relevant. The cells of the kidneys are slowly repairing cells; thus, the radiation toxicity may not be manifest for several months. The clinical and pathological features associated with radiation nephropathy, and issues particular to radiation nephropathy following targeted radionuclide therapy, are described here.

Dosimetry in a myeloablative setting.

In clinical therapy trials using high dosages of systemically administered radioactivity to treat cancer, myeloablation may occur. This is either an effect of the circulating radioactivity labeled to antibodies exposing the bone marrow to radiation, or it may occur because malignant cells in the bone marrow are targeted. Bone marrow cells may be targeted through antigens expressed on cells in the bone marrow or because radioactivity is targeted to the skeleton. Assessment of radiation absorbed dose to the marrow may be useful for dose escalation or individualized patient treatment planning. With successful preservation of marrow function with autologous marrow or peripheral blood stem cell transplantation, other normal organs may also receive sufficient radiation to show toxicity. Accurate dose estimates to these organs is important for the design of future studies in order to minimize or avoid toxicity. This paper reviews internally administered high dose radiation therapy studies, and examines the radiation absorbed dose estimates reported from these studies.

Dosimetry of high dose skeletal targeted radiotherapy (STR) with 166Ho-DOTMP.

A study was undertaken to determine the maximum tolerated dose of (166)Ho-DOTMP that could be administered safely, without negatively impacting marrow re-engraftment, in patients with multiple myeloma treated with melphalan prior to transplant. Ho-166 DOTMP is a tetraphosphonate that localizes rapidly to bone surface. The Ho-166 physical half-life is 26.8 hr and the maximum beta energy is 1.8 MeV. Standard dosimetry models were adapted for radiation absorbed dose estimates using data obtained from whole body counting of the low abundance photons emitted by (166)Ho. Eighty-three patients received high dose (166)Ho-DOTMP followed by melphalan and transplant of peripheral blood stem cells. Twenty-five patients also received 8 Gy total body radiation (TBI). Dosages administered ranged from 460 to 4476 mCi (166)Ho-DOTMP. Marrow dose was derived using the assumption that all radioactivity not excreted by 20 hours was localized to the bone surfaces, and applying the Eckerman bone and marrow dose model to the calculated bone residence times. The dosimetry of the urinary bladder and kidneys was important because of the rapid excretion of the non-targeted radioactivity via the urinary pathway. The dynamic bladder model was used for bladder wall surface dose, and the ICRP 53 kinetic model was used to model kidney kinetics with an additional blood component included. Marrow doses ranged from 13 to 59 Gy and successful hematapoietic recovery occurred. Bladder doses ranged from 4.7 to 157 Gy. Hemorrhagic cystitis occurred in some patients who received more than 40 Gy to the bladder wall surface. Bladder irrigation was successful in protecting patients from bladder toxicity. Kidney doses ranged from 0.5-7.9 Gy. Kidney toxicity in the form of thrombotic microangiopathy with renal dysfunction was observed, with the severity being related to Ho-166-DOTMP radiation dose and probably the dose rate as well. In a future trial, kidney dosimetry will be assessed using early serial gamma camera imaging and modifications will be implemented to reduce renal toxicity.

Dosimetry model for radioactivity localized to intestinal mucosa.

BACKGROUND: This paper provides a new model for calculating radiation-absorbed doses to the full thickness of the small and large intestinal walls, and to the mucosal layers. The model was used to estimate the intestinal radiation doses from yttrium-90-labeled-DOTA-biotin binding to NR-LU-10-streptavidin in patients. METHODS: We selected model parameters from published data and observations, and used the model to calculate energy-absorbed fractions using the EGS4 radiation transport code. We determined the cumulated (90)Y activity in the small and large intestines of patients from gamma camera images, and calculated absorbed doses to the mucosal layer and to the whole intestinal wall. RESULTS: The mean absorbed dose to the wall of the small intestine was 16.2 mGy/MBq (60 cGy/mCi) administered from (90)Y localized in the mucosa, and 70 mGy/MBq (260 cGy/mCi) to the mucosal layer within the wall. Doses to the large intestinal wall and to the mucosa of the large intestine were lower than those for the small intestine by a factor of about 2.5. These doses are greater by factors of about 5 to 6 than those that would have been calculated using the standard MIRD models that assume the intestinal activity is in the bowel contents. CONCLUSIONS: The specific uptake of radiopharmaceuticals in mucosal tissues may lead to dose-related intestinal toxicities. Tissue dosimetry at the sub-organ level is useful for a better understanding of intestinal tract radiotoxicity and associated dose-response relationships.

Phase II study of picoplatin as second-line therapy for patients with small-cell lung cancer.

PURPOSE: This study was designed to confirm the efficacy and safety of picoplatin, a cisplatin analog designed to overcome platinum resistance, in patients with small-cell lung cancer (SCLC) with platinum-refractory/-resistant disease. PATIENTS AND METHODS: All patients received intravenous picoplatin 150 mg/m(2) every 3 weeks. Tumor response, progression-free survival, and overall survival were evaluated. Adverse events were assessed for frequency, severity, and relationship to treatment. Quality of life was assessed with the Lung Cancer Symptom Scale instrument. RESULTS: Seventy-seven patients were treated with picoplatin (median number of cycles, two; range one to 10). Three patients (4%) had a partial response, 33 (43%) had stable disease (four of these were unconfirmed partial responses), 36 (47%) had progressive disease, and five were not assessable for response. Median progression-free survival was 9.1 weeks (95% CI, 7.0 to 12.1 weeks). Median overall survival was 26.9 weeks (95% CI, 21.1 to 33.4). The most common grade 3 and 4 toxicities were thrombocytopenia (48%), neutropenia (25%), and anemia (20%). The most commonly reported adverse events of any severity included thrombocytopenia (64%), anemia (49%), neutropenia (39%), nausea (27%), fatigue (16%), and dyspnea (16%). No severe neurotoxicity or nephrotoxicity were observed. There were no treatment-related deaths. CONCLUSION: Picoplatin demonstrated clinical efficacy in platinum-refractory SCLC. The major toxicity was hematologic. These results warrant further evaluation in this patient population.

Results of a retrospective single institution analysis of targeted skeletal radiotherapy with (166)Holmium-DOTMP as conditioning regimen for autologous stem cell transplant for patients with multiple myeloma. Impact on transplant outcomes.

(166)Holmium-DOTMP is a beta-emitting radiophosphonate that localizes specifically to the bone surfaces and can deliver high-dose radiation to the bone marrow. Phase I/II trials showed feasibility and tolerability when combined with high-dose melphalan with or without total-body irradiation (TBI) in patients with multiple myeloma (MM) undergoing autologous stem cell transplantation (ASCT). The purpose of this study was to define the potential impact of (166)Holmium-DOTMP on outcomes in patients with MM undergoing ASCT. Retrospective review of transplant outcomes among patients with MM who received an ASCT between January 1998 to December 2001 with either melphalan 200 mg/m(2) or a (166)Holmium-DOTMP containing regimen as part of their initial therapy. Univariate analysis was performed for response, overall survival (OS), and event free survival (EFS). One hundred four patients were identified, of which 41 received a (166)Holmium-DOTMP containing regimen and 63 received melphalan alone. The (166)Holmium-DOTMP patients were divided into 2 groups according to the dose received (<2400 mCi versus > or = 2400 mCi). The (166)Holmium-DOTMP group had a trend towards a higher complete remission (CR) rate compared to patients receiving melphalan alone (51% versus 32%). The median EFS for the low-dose (166)Holmium-DOTMP, the high-dose (166)Holmium-DOTMP, and melphalan alone was 30, 23, and 19 months, respectively; the OS rate at 5 years for the 3 groups was 61%, 40%, and 43%, respectively. (166)Holmium-DOTMP, in combination with high-dose melphalan, can result in higher CR rates when given in optimal doses (<2400 mCi) when compared to melphalan alone, and should be further tested in phase III trials in patients with MM undergoing ASCT.

166Ho-DOTMP plus melphalan followed by peripheral blood stem cell transplantation in patients with multiple myeloma: results of two phase 1/2 trials.

Holmium-166 1, 4, 7, 10-tetraazcyclododecane-1, 4, 7, 10-tetramethylenephosphonate (166Ho-DOTMP) is a radiotherapeutic that localizes specifically to the skeleton and can deliver high-dose radiation to the bone and bone marrow. In patients with multiple myeloma undergoing autologous hematopoietic stem cell transplantation two phase 1/2 dose-escalation studies of high-dose 166Ho-DOTMP plus melphalan were conducted. Patients received a 30 mCi (1.110 Gbq) tracer dose of 166Ho-DOTMP to assess skeletal uptake and to calculate a patient-specific therapeutic dose to deliver a nominal radiation dose of 20, 30, or 40 Gy to the bone marrow. A total of 83 patients received a therapeutic dose of 166Ho-DOTMP followed by autologous hematopoietic stem cell transplantation 6 to 10 days later. Of the patients, 81 had rapid and sustained hematologic recovery, and 2 died from infection before day 60. No grades 3 to 4 nonhematologic toxicities were reported within the first 60 days. There were 27 patients who experienced grades 2 to 3 hemorrhagic cystitis, only 1 of whom had received continuous bladder irrigation. There were 7 patients who experienced complications considered to be caused by severe thrombotic microangiopathy (TMA). No cases of severe TMA were reported in patients receiving in 166Ho-DOMTP doses lower than 30 Gy. Approximately 30% of patients experienced grades 2 to 4 renal toxicity, usually at doses targeting more than 40 Gy to the bone marrow. Complete remission was achieved in 29 (35%) of evaluable patients. With a minimum follow-up of 23 months, the median survival had not been reached and the median event-free survival was 22 months. 166Ho-DOTMP is a promising therapy for patients with multiple myeloma and merits further evaluation.

Phase 1 trial of a novel anti-CD20 fusion protein in pretargeted radioimmunotherapy for B-cell non-Hodgkin lymphoma.

Pretargeted radioimmunotherapy (PRIT) has the potential to increase the dose of radionuclide delivered to tumors while limiting radiation to normal tissues. The purpose of this phase 1 trial is to assess safety of this multistep approach using a novel tetrameric single-chain anti-CD20-streptavidin fusion protein (B9E9FP) as the targeting moiety in patients with B-cell non-Hodgkin lymphoma (NHL), and to characterize its pharmacokinetics and immunogenicity. All patients received B9E9FP (160 mg/m(2) or 320 mg/m(2)); either 48 or 72 hours later, a synthetic clearing agent (sCA) was administered (45 mg/m(2)) to remove circulating unbound B9E9FP. (90)Yttrium ((90)Y; 15 mCi/m(2))/(111)In (5 mCi)-DOTA-biotin was injected 24 hours later. There were 15 patients enrolled in the study. B9E9FP had a mean plasma half-life (T(1/2)) of 25 +/- 6 hours with a reduction in plasma level of more than 95% within 6 hours of sCA administration. (90)Y/(111)In-DOTA-biotin infusion resulted in rapid tumor localization and urinary excretion. The ratio of average tumor to whole-body radiation dose was 49:1. No significant hematologic toxicities were noted in 12 patients. There were 2 patients who had hematologic toxicity related to progressive disease. There were 2 complete remissions (90 and 325 days) and one partial response (297 days). B9E9FP performs well as the targeting component of PRIT with encouraging dosimetry, safety, and efficacy. A dose escalation trial of (90)Y-DOTA-biotin in this format is warranted.