Renal and Intestinal Excretion of 90Y and 166Ho After Transarterial Radioembolization of Liver Tumors.

OBJECTIVE. The aim of this study was to evaluate the amount of free radioactivity in renal and intestinal excretions during the first 48 hours after transarterial radioembolization (TARE) procedures on the liver. SUBJECTS AND METHODS. Urinary, intestinal, and biliary excretions of patients who underwent TARE with three different types of microspheres were collected during a postinterventional period of 48 hours (divided into two 24-hour intervals). Radioactivity measurements were performed. The detected amounts of activity were correlated to clinical and procedural characteristics, times of excretion, and microsphere types. RESULTS. Twenty-four patients were evaluated, 10 treated with 90Y-glass, 10 with 90Y-resin, and four with 166Ho-poly-L-lactic acid (PLLA) microspheres. Activity excretion occurred in all cases. The highest total excretion proportions of the injected activities were 0.011% for 90Y-glass, 0.119% for 90Y-resin, and 0.005% for 166Ho-PLLA microspheres. Intestinal excretion was markedly less than renal excretion (p < 0.001). Excretion after TARE with 90Y-resin was statistically significantly higher than with 90Y-glass or 166Ho-PLLA micro-spheres (p = 0.002). For each microsphere type, the excreted activity was independent of the activity of the injected microspheres. CONCLUSION. Renal and intestinal excretion of radioactivity after TARE is low but not negligible. The radiation risk for individuals interacting with patients can be minimized if contact with urine and bile is avoided, particularly during the first 24 hours after the procedure.

Urinary Excretion of Yttrium-90 after Radioembolization with Yttrium-90-Labeled Resin-based Microspheres.

In radioembolic therapy (RET) of hepatic malignancies using yttrium-90 (Y)-labeled resin microspheres, radiation protection is primarily concerned with avoiding contamination by radioactive spheres. However, as Y is bound to the microsphere surface by a potentially reversible ion-exchange process, the aim of this study was to assess the extent of the potential excreted activity in urine. After RET with Y-labeled resin-based microspheres, urinary excretion of free Y was prospectively analyzed in 51 interventions (n = 45 patients) by sampling urine over 48 h (two 24-h intervals) consecutively. The measured urinary concentration of Y, normalized to the administered microsphere activity, was a median of 58.5 kBq L GBq (range = 3.5-590.9 kBq L GBq) and 17.8 kBq L GBq (1.8-58.8 kBq L GBq) for the first and second 24-h periods after administration, respectively (p ≤ 0.0001, F = 28.4, result from ANOVA). The total excreted activity significantly decreased (p ≤ 0.0001) from a median of 72.5 kBq in the first 24-h period to a median of 22.1 kBq in the second 24-h period. Urinary excretion of free Y after resin-based RET occurs for a longer period and at a higher activity excretion than previously published, which has to be considered when patients are either hospitalized or return home after RET. Existing approaches for patient hospitalization, especially in temporary radiation protection areas, justified by the previously reported lower excretion rate, should be re-evaluated, and as a consequence, the current product safety information and handling recommendations for Y-labeled resin-based microspheres may need to be revised.

Intra-arterial treatment with 9°Y microspheres for hepatocellular carcinoma: 4 years experience at the Ghent University Hospital.

PURPOSE: We report on our experience in terms of eligibility, safety, response and survival for treatment of hepatocellular carcinoma (HCC) with (90)Y microspheres. Secondly, we investigated the urinary excretion of (90)Y following treatment. METHODS: We retrospectively reviewed all HCC patients referred to our department for (90)Y microsphere treatment. We recorded reasons for not proceeding to actual treatment. In case treatment was performed, we assessed the tolerance (Common Terminology Criteria for Adverse Events v3.0, CTCAE v3.0), the response [modified Response Evaluation Criteria in Solid Tumors (mRECIST) criteria] and long-term survival (Kaplan-Meier). The urinary excretion was estimated by 12-h urine collections post-injection for analysis in a gamma counter. RESULTS: Forty-three HCC patients were referred for radioembolization. Fourteen patients were excluded, mainly due to unfavourable (99m)Tc-macroaggregated albumin (MAA) distribution. Twenty-nine patients were treated with (90)Y microspheres (TheraSphere, mean activity 2.17 GBq). In four patients severe clinical adverse events were encountered, however only in one case clearly related to the therapy. Twenty patients were assessable by mRECIST: complete response in 15%, partial response in 35%, stable disease in 30% and progression in 20% were observed. A median survival of 12.3 months (95% confidence interval 9.4-15.2) was estimated. Concerning the substudy on urinary excretion, only 0.0025% of the administered activity was excreted in the urine within the first 12 h following TheraSphere. CONCLUSION: Following a strict workup before admitting patients to radioembolization with TheraSphere, we found good clinical tolerance in the vast majority of patients. Radiological response assessment yielded an overall response rate of 50%, when evaluated early following treatment. Urine analysis showed consistently only low activities of (90)Y excreted in the urine.

Preliminary studies of an 18-crown-6 ether modified magnetic cation exchange polymer in rapid (90)Sr bioassay.

A cation exchange polymer resin embedded with magnetic nanoparticles and modified with crown ether was developed for urinalysis to rapidly monitor levels of (90)Sr exposure in humans who have been involved in a nuclear event. Invention of the resin matrix of 2-acrylamido-2-methyl-1-propanesulfonic acid cross-linked with divinylbenzene incorporated a Sr(2+) chelating agent, di-tert-butyl-cyclohexano-18-crown-6 through surface immobilization using a molecular modifier 1-octanol. The performance of these magnetic cation exchange resin particles was investigated by separating (90)Sr in the presence of (90)Y progeny. Masking agents and precipitants were examined to ascertain that sodium hydroxide at pH 7.5 was capable of selectively removing 89 ± 2% (90)Y before subsequent (90)Sr uptake. Preliminary investigations in rapid urinalysis were successful in isolating 83 ± 2% (90)Sr when pH was optimized to 9, with a sample turnover time <2 h, which is promising for radiological emergencies.

[Radiation exposure in (90)Y-Zevalin therapy: results of a prospective multicentre trial]. / Strahlenexposition bei der (90)Y-Zevalin-Therapie: Ergebnisse einer prospektiven multizentrischen Studie.

UNLABELLED: AIM of this study was the assessment of the radiation exposure from preparation and application of (90)Y-Zevalin, the measurement of the dose rate at the patient, the exposure of family members as well as the determination of the activity concentration in urine of patients. METHODS: Overall data from 31 therapeutic administrations carried out in four institutions were evaluated. During preparation and application of (90)Y-Zevalin the finger exposures of radiochemists, technicians, and physicians were measured. The dose rate of the patient was measured immediately after radioimmunotherapy. In patients treated in a nuclear medicine therapy unit, urine was collected over a two day period and the corresponding activity was determined. Family members of outpatients were asked to wear a dosimeter over a seven day period. RESULTS: During the preparation we found a maximum skin dose of 6 mSv at the average, and during application of 3 mSv, respectively. After administration of (90)Y the dose rate was 0.4 +/- 0.1 microSv/h at 2 m distance. Urine measurements yielded a cumulated 24 h excretion of 3.9 +/- 1.4% and 4.4 +/- 1.4% within 48 h, respectively, that is equivalent to 43 +/- 18 and 50 +/- 20 MBq of (90)Y, respectively. Family members received a radiation exposure of 40 +/- 14 microSv over seven days. CONCLUSION: During preparation and application of (90)Y-Zevalin appropriate radiation shielding is necessary. For family members as well as nursing staff no additional special radiation protection measures beyond those being common for other nuclear medicine procedures are necessary.

Quantitation in PET using isotopes emitting prompt single gammas: application to yttrium-86.

Several yttrium-90 labelled somatostatin analogues are now available for cancer radiotherapy. After injection, a large amount of the compound is excreted via the urinary tract, while a variable part is trapped in the tumour(s), allowing the curative effect. Unfortunately, the compound may also be trapped in critical tissues such as kidney or bone marrow. As a consequence, a method for assessment of individual biodistribution and pharmacokinetics is required to predict the maximum dose that can be safely injected into patients. However, (90)Y, a pure beta(-)particle emitter, cannot be used for quantitative imaging. Yttrium-86 is a positron emitter that allows imaging of tissue uptake using a PET camera. In addition to the positron, (86)Y also emits a multitude of prompt single gamma-rays, leading to significant overestimation of uptake when using classical reconstruction methods. We propose a patient-dependent correction method based on sinogram tail fitting using an (86)Y point spread function library. When applied to abdominal phantom acquisition data, the proposed correction method significantly improved the accuracy of the quantification: the initial overestimation of background activity by 117% was reduced to 9%, while the initial error in respect of kidney uptake by 84% was reduced to 5%. In patient studies, the mean discrepancy between PET total body activity and the activity expected from urinary collections was reduced from 92% to 7%, showing the benefit of the proposed correction method.

86Y-DOTA0)-D-Phe1-Tyr3-octreotide (SMT487)--a phase 1 clinical study: pharmacokinetics, biodistribution and renal protective effect of different regimens of amino acid co-infusion.

The pharmacokinetics and dosimetry of (86)Y-DOTA(0)- d-Phe(1)-Tyr(3)-octreotide ((86)Y-SMT487) were evaluated in a phase I positron emission tomography (PET) study of 24 patients with somatostatin receptor-positive neuroendocrine tumours. The effect of amino acid (AA) co-infusion on renal and tumour uptake was assessed in a cross-over randomised setting. Five regimens were tested: no infusion, 4-h infusion of 120 g mixed AA (26.4 g l-lysine + l-arginine), 4 h l-lysine (50 g), 10 h 240 g mixed AA (52.8 g l-lysine + l-arginine) and 4 h Lys-Arg (25 g each). Comparisons were performed on an intra-patient basis. Infusions of AA started 0.5 h prior to injection of (86)Y-SMT487 and PET scans were obtained at 4, 24 and 48 h p.i. Absorbed doses to tissues were computed using the MIRD3 method. (86)Y-SMT487 displayed rapid plasma clearance and exclusive renal excretion; uptake was noted in kidneys, tumours, spleen and, to a lesser extent, liver. The 4-h mixed AA co-infusion significantly ( P<0.05) reduced (86)Y-SMT487 renal uptake by a mean of 21%. This protective effect was significant on the dosimetry data (3.3+/-1.3 vs 4.4+/-1.0 mGy/MBq; P<0.05) and was further enhanced upon prolonging the infusion to 10 h (2.1+/-0.4 vs 1.7+/-0.2 mGy/MBq; P<0.05). Infusion of Lys-Arg but not of l-lysine was more effective in reducing renal uptake than mixed AA. Infusion of AA did not result in reduced tumour uptake. The amount of (90)Y-SMT487 (maximum allowed dose: MAD) that would result in a 23-Gy cut-off dose to kidneys was calculated for each study: MAD was higher with mixed AA co-infusion by a mean of 46% (10-114%, P<0.05 vs no infusion). In comparison with 4 h mixed AA, the MAD was higher by a mean of 23% (9-37%; P<0.05) with prolonged infusion and by a mean of 16% (2-28%; P<0.05) with Lys-Arg. We conclude that infusion of large amounts of AA reduces renal exposure during peptide-based radiotherapy and allows higher absorbed doses to tumours. The prolongation of the infusion from 4 to 10 h further enhances the protective effect on the kidneys.

Intrapatient consistency of imaging biodistributions and their application to predicting therapeutic doses in a phase I clinical study of 90Y-based radioimmunotherapy.

Intrapatient variation in the biodistribution of the chimeric monoclonal antibody cT84.66 was assessed in 19 patients having a variety of carcinoembryonic antigen (CEA) positive tumors. The two studies, including whole-body imaging and blood and urine specimen collections, were conducted within 14 days of each other using (111)In-cT84.66 at a fixed total protein dose of 5 mg per patient per study. An initial pretherapy infusion of (111)In-cT84.66 was administered followed by a therapy coinfusion of (111)In-ct84.66 and 90Y-cT84.66 A closed five-compartment model was used to integrate source organ activity curves as residence time inputs into the MIRDOSE3 program. Normal organ absorbed doses were estimated for 90Y-cT84.66, the corresponding radiotherapeutic agent. For the two (111)In-cT84.66 biodistributions, all data were modeled with a R2 value of between 0.72 and 1.00 with the exception of the urine data taken during therapy. This was due to the need of diethylenetriaminepentaacetic acid during the therapy phase because of the possibility that yttrium might escape from the chelator attached to the antibody. With the assurance that the biodistributions were reproducible, we were able to estimate the 90Y-cT84.66 absorbed doses on a per-patient basis. Concordance coefficients showing the agreement between the imaging and therapy phase dose estimates were between the 0.60 and 0.99 levels for liver, spleen, red marrow, total body, and other organ systems. Median results were: 27, 17, and 2.7 rad/mCi of 90Y-cT84.66 for liver, spleen, and red marrow, respectively. Because of decreases in platelets and white cells as the amount of 90Y was increased, dose-limiting toxicity was found at 22 mCi/m2. We conclude that patient biodistributions were consistent over time to 14 days so as to allow absorbed dose estimation in a radioimmunotherapy trial involving the cT84.66 anti-CEA antibody.

90Y-resin particles--animal experiments on pigs with regard to the introduction of superselective embolization therapy.

Resin particles (diameter 45-75 microns) were labelled with 90Y, suspended in a glucose/dextran solution and infused into the kidneys of 3-month-old pigs (tumour model). Both kidneys of each animal were embolized with particles, but only one with active (90Y loaded) particles and the other, for comparison, with inactive particles. The organ measurements showed less than 1% of injected activity in bone, bone marrow, liver and lung compared to greater than 99% retention by the kidneys. Only minimal shunted activity was found in blood (less than 0.27%) and urine (less than 0.07%). There was a clear shrinkage of the 90Y-treated kidneys with a reduction in weight of up to 50%. Histologically, the ischaemic lesions (infarcts and atrophy) were clearly more pronounced and extensive in the 90Y-embolized kidneys than in the non-radioactive embolized kidneys. Furthermore, severe arterial wall changes and fibrotic necrosis due to radiation damage were observed in the 90Y-treated kidneys. It is concluded that with intra-arterially applied particles a dose of about 100 Gy is sufficient to completely destroy tissue-specific structures. Complications due to acute necrosis or inflammatory reactions were not observed, and there were no shunt related alterations seen in the liver or lungs. The 90Y-loaded resin particles are considered suitable for a super selective intra-arterial radioembolization.

90Yttrium antiferritin--a new therapeutic radiolabeled antibody.

A new radiolabel 90Yttrium has been chelated to antiferritin antibodies for the treatment of hepatocellular cancer. The isotope 90Yttrium has the advantage of no significant external radiation to other individuals, that is, outpatient therapy and potentially more therapeutic power with an increase from 0.3 Mev 131I beta radiation to 0.9 Mev 90Yttrium pure beta radiation. Six patients treated in the Phase I study have had modest hematologic toxicity and two have had partial remissions of their primary tumors. One of these patients has had complete remission of a pulmonary metastasis. The use of external radiation (900 rad) to the primary tumor in advance of radiolabeled antibody administration has increased antibody uptake and increased tumor dose rate and total dose. An extensive study of 90Yttrium antiferritin is planned.

Retention and extra-articular spread of intra-articularly injected 90Y silicate.

A study was performed on the retention and distribution of intra-articularly injected colloidal 90Y silicate in 7 patients with rheumatoid arthritis (8 knees). In 5 knees retention was complete within the limits of measuring accuracy, and in the remaining 3, 82-84% was retained. No radioactivity was detected in the liver and heart areas or in the blood samples. The cumulative urine activity was less than 1.8%. In the inguinal lymph nodes, activity was detectable %0.5-2%) in only 3 cases. We conclude that 90Y silicate is a safe radioactive agent for the treatment of knee effusions, provided the limb is strictly immobilized after the injection.