Medical Internal Radiation Dose Formalism Research Articles

A Review of Organ Dose Calculation Methods and Tools for Patients Undergoing Diagnostic Nuclear Medicine Procedures

Exponential growth has been observed in nuclear medicine procedures worldwide in the past decades. The considerable increase is attributed to the advance of positron emission tomography and single photon emission computed tomography, as well as the introduction of new radiopharmaceuticals. Although nuclear medicine procedures provide undisputable diagnostic and therapeutic benefits to patients, the substantial increase in radiation exposure to nuclear medicine patients raises concerns about potential adverse health effects and calls for the urgent need to monitor exposure levels. In the current article, model-based internal dosimetry methods were reviewed, focusing on Medical Internal Radiation Dose (MIRD) formalism, biokinetic data, human anatomy models (stylized, voxel, and hybrid computational human phantoms), and energy spectrum data of radionuclides. Key results from many articles on nuclear medicine dosimetry and comparisons of dosimetry quantities based on different types of human anatomy models were summarized. Key characteristics of seven model-based dose calculation tools were tabulated and discussed, including dose quantities, computational human phantoms used for dose calculations, decay data for radionuclides, biokinetic data, and user interface. Lastly, future research needs in nuclear medicine dosimetry were discussed. Model-based internal dosimetry methods were reviewed focusing on MIRD formalism, biokinetic data, human anatomy models, and energy spectrum data of radionuclides. Future research should focus on updating biokinetic data, revising energy transfer quantities for alimentary and gastrointestinal tracts, accounting for body size in nuclear medicine dosimetry, and recalculating dose coefficients based on the latest biokinetic and energy transfer data.

Concepts and methods for the dosimetry of radioembolisation of the liver with Y-90-loaded microspheres

This article aims at presenting in a didactic way, dosimetry concepts and methods that are relevant for radio-embolization of the liver with 90Y-microspheres. The application of the medical internal radiation dose formalism to radio-embolization is introduced. This formalism enables a simplified dosimetry, where the absorbed dose in a given tissue depends on only its mass and initial activity. This is applied in the single-compartment method, partition model, for the liver, tumour and lung dosimetry, and multi-compartment method, allowing identification of multiple tumours. Voxel-based dosimetry approaches are also discussed. This allows taking into account the non-uniform uptake within a compartment, which translates into a non-uniform dose distribution, represented as a dose–volume histogram. For this purpose, dose–kernel convolution allows propagating the energy deposition around voxel-sources in a computationally efficient manner. Alternatively, local-energy deposition is preferable when the spatial resolution is comparable or larger than the beta-particle path. Statistical tools may be relevant in establishing dose–effect relationships in a given population. These include tools such as the logistic regression or receiver operator characteristic analysis. Examples are given for illustration purpose. Moreover, tumour control probability modelling can be assessed through the linear-quadratic model of Lea and Catcheside and its counterpart, the normal-tissue complication probability model of Lyman, which is suitable to the parallel structure of the liver. The selectivity of microsphere administration allows tissue sparing, which can be considered with the concept of equivalent uniform dose, for which examples are also given. The implication of microscopic deposition of microspheres is also illustrated through a liver toxicity model, even though it is not clinically validated. Finally, we propose a reflection around the concept of therapeutic index (TI), which could help tailor treatment planning by determining the treatment safety through the evaluation of TI based on treatment-specific parameters.

Relationship of In Vitro Toxicity of Technetium-99m to Subcellular Localisation and Absorbed Dose.

Auger electron-emitters increasingly attract attention as potential radionuclides for molecular radionuclide therapy in oncology. The radionuclide technetium-99m is widely used for imaging; however, its potential as a therapeutic radionuclide has not yet been fully assessed. We used MDA-MB-231 breast cancer cells engineered to express the human sodium iodide symporter-green fluorescent protein fusion reporter (hNIS-GFP; MDA-MB-231.hNIS-GFP) as a model for controlled cellular radionuclide uptake. Uptake, efflux, and subcellular location of the NIS radiotracer [99mTc]TcO4− were characterised to calculate the nuclear-absorbed dose using Medical Internal Radiation Dose formalism. Radiotoxicity was determined using clonogenic and γ-H2AX assays. The daughter radionuclide technetium-99 or external beam irradiation therapy (EBRT) served as controls. [99mTc]TcO4− in vivo biodistribution in MDA-MB-231.hNIS-GFP tumour-bearing mice was determined by imaging and complemented by ex vivo tissue radioactivity analysis. [99mTc]TcO4− resulted in substantial DNA damage and reduction in the survival fraction (SF) following 24 h incubation in hNIS-expressing cells only. We found that 24,430 decays/cell (30 mBq/cell) were required to achieve SF0.37 (95%-confidence interval = [SF0.31; SF0.43]). Different approaches for determining the subcellular localisation of [99mTc]TcO4− led to SF0.37 nuclear-absorbed doses ranging from 0.33 to 11.7 Gy. In comparison, EBRT of MDA-MB-231.hNIS-GFP cells resulted in an SF0.37 of 2.59 Gy. In vivo retention of [99mTc]TcO4− after 24 h remained high at 28.0% ± 4.5% of the administered activity/gram tissue in MDA-MB-231.hNIS-GFP tumours. [99mTc]TcO4− caused DNA damage and reduced clonogenicity in this model, but only when the radioisotope was taken up into the cells. This data guides the safe use of technetium-99m during imaging and potential future therapeutic applications.

Influence of dosimetry method on bone lesion absorbed dose estimates in PSMA therapy: application to mCRPC patients receiving Lu-177-PSMA-I&T

BackgroundPatients with metastatic, castration-resistant prostate cancer (mCRPC) present with an increased tumor burden in the skeleton. For these patients, Lutetium-177 (Lu-177) radioligand therapy targeting the prostate-specific membrane antigen (PSMA) has gained increasing interest with promising outcome data. Patient-individualized dosimetry enables improvement of therapy success with the aim of minimizing absorbed dose to organs at risk while maximizing absorbed dose to tumors. Different dosimetric approaches with varying complexity and accuracy exist for this purpose. The Medical Internal Radiation Dose (MIRD) formalism applied to tumors assumes a homogeneous activity distribution in a sphere with unit density for derivation of tumor S values (TSV). Voxel S value (VSV) approaches can account for heterogeneous activities but are simulated for a specific tissue. Full patient-individual Monte Carlo (MC) absorbed dose simulation addresses both, heterogeneous activity and density distributions. Subsequent CT-based density weighting has the potential to overcome the assumption of homogeneous density in the MIRD formalism with TSV and VSV methods, which could be a major limitation for the application in bone metastases with heterogeneous density. The aim of this investigation is a comparison of these methods for bone lesion dosimetry in mCRPC patients receiving Lu-177-PSMA therapy.ResultsIn total, 289 bone lesions in 15 mCRPC patients were analyzed. Percentage difference (PD) of average absorbed dose per lesion compared to MC, averaged over all lesions, was + 14 ± 10% (min: − 21%; max: + 56%) for TSVs. With lesion-individual density weighting using Hounsfield Unit (HU)-to-density conversion on the patient’s CT image, PD was reduced to − 8 ± 1% (min: − 10%; max: − 3%). PD on a voxel level for three-dimensional (3D) voxel-wise dosimetry methods, averaged per lesion, revealed large PDs of + 18 ± 11% (min: − 27%; max: + 58%) for a soft tissue VSV approach compared to MC; after voxel-wise density correction, this was reduced to − 5 ± 1% (min: − 12%; max: − 2%).ConclusionPatient-individual MC absorbed dose simulation is capable to account for heterogeneous densities in bone lesions. Since the computational effort prevents its routine clinical application, TSV or VSV dosimetry approaches are used. This study showed the necessity of lesion-individual density weighting for TSV or VSV in Lu-177-PSMA therapy bone lesion dosimetry.

Absorbed dose simulation of meta-211At-astato-benzylguanidine using pharmacokinetics of 131I-MIBG and a novel dose conversion method, RAP.

We aimed to estimate in vivo 211At-labeled meta-benzylguanidine (211At-MABG) absorbed doses by the two dose conversion methods, using 131I-MIBG biodistribution data from a previously reported neuroblastoma xenograft model. In addition, we examined the effects of different cell lines and time limitations using data from two other works. We used the framework of the Monte Carlo method to create 3200 virtual experimental data sets of activity concentrations (kBq/g) to get the statistical information. Time activity concentration curves were produced using the fitting method of a genetic algorithm. The basic method was that absorbed doses of 211At-MABG were calculated based on the medical internal radiation dose formalism with the conversion of the physical half-life time of 131I to that of 211At. We have further improved the basic method; that is, a novel dose conversion method, RAP (Ratio of Pharmacokinetics), using percent injected dose/g. Virtual experiments showed that 211At-MABG and 131I-MIBG had similar properties of initial activity concentrations and biological components, but the basic method did not simulate the 211At-MABG dose. Simulated 211At-MABG doses from 131I-MIBG using the RAP method were in agreement with those from 211At-MABG, so that their boxes overlapped in the box plots. The RAP method showed applicability to the different cell lines, but it was difficult to predict long-term doses from short-term experimental data. The present RAP dose conversion method could estimate 211At-MABG absorbed doses from the pharmacokinetics of 131I-MIBG with some limitations. The RAP method would be applicable to a large number of subjects for targeted nuclide therapy.

Empirical 188Re-HDD/lipiodol intra-arterial therapy based on tumor volume, in patients with solitary inoperable hepatocellular carcinoma.

This study aimed to assess the potential benefits and tolerability of an empirical dose of approximately 0.8-1.2 mCi (29.6-44.4 MBq) of Re-4-hexadecyl-1-2,9,9-tetramethyl-4,7-diaza-1,10-decanethiol/lipiodol (Re-HDD/lipiodol) per milliliter of tumor volume, administered after super-selection of the tumor feeding branches of hepatic artery for treatment of inoperable hepatocellular carcinoma (HCC). Patients with advanced HCC or classified as inoperable, with no demonstrated extrahepatic disease and no significant comorbidities were eligible. The patients selected for this study had a single tumoral lesion, measuring less than 150 cc. The range of total activity administered was between 30 and 100 mCi (1.2-3.7) GBq Re-HDD/lipiodol, administered in the super selected branches of the hepatic artery supplying the tumor in 42 Patients. Whole-body scintigraphies and single-photon emission computed tomography-computed tomography (SPECT-CT) of the liver including tumor were performed at four-time points after injection. Absorbed doses to the various organs were calculated according to the Medical Internal Radiation Dose formalism. Blood and urine samples were collected at multiple time points until 72 h after injection. Hematological, hepatic and pulmonary toxicity was assessed until 12 weeks after administration using the Common Toxicity Criteria for Adverse Events (version 3.0) scale. Responses were evaluated on contrast enhanced computed tomography (CECT) and by alfa-fetoprotein (AFP) level monitoring. About 40.6 ± 4.8% of the injected activity was excreted in the urine by 72 h after injection. The mean absorbed dose to the liver, lungs, stomach, kidney and intestine was 14.4 ± 1.8, 4.8 ± 0.6, 5.5 ± 1.1, 5.1 ± 0.7, and 6.5 ± 1.0 Gy (mean ± SD), respectively. Up to 6 days after administration, 26 of 44 patients had adverse events consisting of aggravations of preexisting laboratory changes (24 patients), fatigue (5 patients), vomiting (6 patients), fever (2 patients), right hypochondrial pain (8 patients), and pain at site of femoral catheter insertion (8 patients). Toxicity assessment at weeks 6 and 12 revealed two cases of mild worsening of liver function tests and no lung or hematological toxicity noted. Two patients were lost to follow-up after the 6-week visit. The response was assessed on CECT in all the remaining patients and the classification of results was more standardized when using European Association for the Study of the Liver (EASL) criteria rather than response evaluation criteria in solid tumors (RECIST) criteria. According to EASL criteria, 8 patients had a partial response, 28 patients had a complete response, 4 patients had progressive disease and 4 patients with stable disease were reported. Thirty-six patients had a baseline elevated AFP and on follow-up at 6 weeks, 6 of these patients showed stable AFP, progression in 4 patients and 26 showed a reduction. After the administration of 1.2-3.7 GBq Re-HDD/lipiodol based on empirical activity calculation of 0.8-1.2 mCi/mL of tumor volume, more than half of the patients in the present study had an objective response on imaging and biochemically. No significant adverse side effects were noted and most of the laboratory markers as well as symptoms returned to normal after 48-72 h post-administration. Selective administration of the radiopharmaceutical into the tumor feeding arteries gives a good anti-tumoral effect with minimal side effects and damage to surrounding normal liver tissue.

Dosimetric analysis of (123)I, (125)I and (131)I in thyroid follicle models.

BackgroundRadioiodine is routinely used or proposed for diagnostic and therapeutic purposes: 123I, 125I and 131I for diagnostics and 125I and 131I for therapy. When radioiodine-labelled pharmaceuticals are administered to the body, radioiodide might be released into the circulation and taken up by the thyroid gland, which may then be an organ at risk. The aim of this study was to compare dosimetric properties for 123I, 125I and 131I in previously developed thyroid models for man, rat and mouse.MethodsDosimetric calculations were performed using the Monte Carlo code MCNPX 2.6.0 and nuclear decay data from ICRP 107. Only the non-radiative transitions in the decays were considered. The S value was determined for the cell nuclei in species-specific thyroid follicle models for mouse, rat and man for different spatial distributions of radioiodine.ResultsFor the species-specific single follicle models with radioiodine homogeneously within the follicle lumen, the highest S value came from 131I, with the largest contribution from the β particles. When radioiodine was homogeneously distributed within the follicle cells or the follicle cell nucleus, the highest contribution originated from 125I, about two times higher than 123I, with the largest contribution from the Auger electrons. The mean absorbed dose calculated for our human thyroid multiple follicle model, assuming homogenous distribution of for 123I, 125I, or 131I within the follicle lumens and follicle cells, was 9%, 18% and 4% higher, respectively, compared with the mean absorbed dose according to Medical Internal Radiation Dose (MIRD) formalism and nuclear decay data. When radioiodine was homogeneously distributed in the follicle lumens, our calculations gave up to 90% lower mean absorbed dose for 125I compared to MIRD (20% lower for 123I, and 2% lower for 131I).ConclusionsThis study clearly demonstrates the importance of using more detailed dosimetric methods and models than MIRD formalism for radioiodine, especially 123I and 125I, in the thyroid. For radioiodine homogeneously distributed in the follicle lumens our calculations for the human multiple follicle models gave up to 90% lower mean absorbed dose compared with MIRD formalism.

Radioiodine Therapy for Graves Disease

Based on the committed thyroid absorbed dose, the aim was to compare the efficiency of I therapy against Graves disease (GD) within 1 year after treatment and, by exploring the dose-response relationship, indicate an absorbed dose to be targeted into patient therapeutic planning. Thyroid-absorbed doses were calculated to 196 patients with GD by applying Medical Internal Radiation Dose formalism and taking into account administered I activity, thyroid radioiodine uptake, effective half-life, and gland tissue mass. Statistical analysis was applied to assess the relationship between absorbed doses and the patient's clinical response. Overall, successful therapy was achieved in 167 patients, whereas in 29 the disease persisted, even though 64.8% and 89.3% of all the treated patients had received, respectively, thyroid absorbed dose and activity superior to 300 Gy and 11.1 MBq/g (300 μCi/g) of thyroid tissue. Among those in whom the disease persisted, 24 (83%) had a 6- to 24-hour I uptake ratio equal or superior to 0.9, whereas only 5 (17%) presented a lower ratio. According to statistical analysis, there was no difference in cure rate between the groups that received 300 Gy or less and that which received more (84.1% vs 85.8%, P = 0.8336). A thyroid absorbed dose of 300 Gy is plausible as a targeted therapeutic dose in GD therapy planning, because statistical analysis has proven there to be no advantage in treating patients with doses above this level. On the other hand, numerous efforts should be made to develop an optimized and easily applicable protocol of patient-specific dosimetry and to provide data that show its clinical impact on patient management.

Pharmacokinetics of 131 I-labeled-metuximab and transarterial chemoembolization for treatment of hepatocellular carcinoma

Objective: To study the pharmacokinetics of {sup 131}I-Metuximab injection (Licartin) combined with transarterial chemoembolization (TACE) for treatment of hepatocellular carcinoma (HCC). Methods: Licartin (27.75 MBq/kg) and the mixture of anticancer drug and Lipiodol were sequentially administered with interval of 20 minutes to 15 patients with HCC via a transfemoral catheter. After the Licartin was administrated, the pharmacokinetic and biodistribution data were evaluated through venous blood samples, urine collections,and 4 {gamma}-scintigraphies (SPECT) over 7 days. The pharmacokinetic parameters were determined from integration of the blood radioactivity-time curves using the SPSS 12.0 software. The tumor-no-tumor ratio (T/NT) was calculated by ROI. Absorbed doses in organ were estimated according to the medical internal radiation dose formalism. The biodistribution of licartin within patient's body at different time points was compared for various organs using analysis of variance for repeated measures, as well as the T/NT ratio. Results: The blood radioactivity-time curves followed the dynamics two-compartment model, with the major pharmacokinetic parameters including t{sub (1/2)} {alpha} (1.96 {+-} 1.65) h, and t{sub 1/2} {alpha} (19.07 {+-} 5.91) h, and t{sub 1/2} {beta} (57.09 {beta} 10.92) h, and C{sub max} 2.113 x 10{sup 9}min{sup -1} {center_dot} L{sup -1}, and AUC{sub 0-{infinity}} 1.302 x 10{sup 11} h {center_dot} min{sup -1} {center_dot} L{sup -1}, respectively. The accumulated urine radioactivity was 52.2% of administrated dosage during 144 h after administration. There were statistical significant difference of biodistribution of licartin and T/NT ratio between organs at different time points (F=6.583, P<0.01 and F=3.546, P<0.01). SPECT scans showed the significant accumulation of the radioconjugate in liver tumor and faint uptake in other organs for 14 days. Tumor-to-liver ratio decreased from 2.88 {+-} 1.02 at 3 h to 1.64 {+-} 0.40 at 168 h (n=7). Organ absorbed dose was (3.19 {+-} 1.01) Gy in liver (n=12) and (0.55 {+-} 0.09) Gy in red marrow (n=7). Conclusion: Licartin combined with TACE for treatment of HCC is helpful to significantly accrete the radioconjugate in liver tumor, and protect normal organs from radiotoxictiy. (authors)

Intraoperative Avidination for Radionuclide Therapy: A Prospective New Development to Accelerate Radiotherapy in Breast Cancer

In a continuous effort to seek for anticancer treatments with minimal side effects, we aim at proving the feasibility of the Intraoperative Avidination for Radionuclide Therapy, a new procedure for partial breast irradiation. To assess doses of 90Y-DOTA-biotin to target (i.e., breast tumor bed) and nontarget organs, we did simulation studies with 111In-DOTA-biotin in 10 candidates for conservative breast surgery. Immediately after quadrantectomy, patients were injected with 100-mg avidin in the tumor bed. On the following day, patients were given 111In-DOTA-biotin (approximately 111 MBq) i.v. after appropriate chase of biotinylated albumin (20 mg) to remove circulating avidin. Biokinetic studies were done by measuring radioactivity in scheduled blood samples, 48-h urine collection, and through scintigraphic images. The medical internal radiation dose formalism (OLINDA code) enabled dosimetry assessment in target and nontarget organs. Images showed early and long-lasting radioactive biotin uptake in the operated breast. Rapid blood clearance (<1% at 12 h) and urine excretion (>75% at 24 h) were observed. Absorbed doses, expressed as mean+/-SD in Gy/GBq, were as low as 0.15+/-0.05 in lungs, 0.10+/-0.02 in heart, 0.06+/-0.02 in red marrow, 1.30+/-0.50 in kidneys, 1.50+/-0.30 in urinary bladder, and 0.06+/-0.02 in total body, whereas in the targeted area, they increased to 5.5+/-1.1 Gy/GBq (50% ISOROI) and 4.8+/-1.0 Gy/GBq (30% ISOROI). Our preliminary results suggest that Intraoperative Avidination for Radionuclide Therapy is a simple and feasible procedure that may improve breast cancer patients' postsurgical management by shortening radiotherapy duration.

Biological optimization of heterogeneous dose distributions in systemic radiotherapy

The standard computational method developed for internal radiation dosimetry is the MIRD (medical internal radiation dose) formalism, based on the assumption that tumor control is given by uniform dose and activity distributions. In modern systemic radiotherapy, however, the need for full 3D dose calculations that take into account the heterogeneous distribution of activity in the patient is now understood. When information on nonuniform distribution of activity becomes available from functional imaging, a more patient specific 3D dosimetry can be performed. Application of radiobiological models can be useful to correlate the calculated heterogeneous dose distributions to the current knowledge on tumor control probability of a homogeneous dose distribution. Our contribution to this field is the introduction of a parameter, the F factor, already used by our group in studying external beam radiotherapy treatments. This parameter allows one to write a simplified expression for tumor control probability (TCP) based on the standard linear quadratic (LQ) model and Poisson statistics. The LQ model was extended to include different treatment regimes involving source decay, incorporating the repair "micro" of sublethal radiation damage, the relative biological effectiveness and the effective "waste" of dose delivered when repopulation occurs. The sensitivity of the F factor against radiobiological parameters (alpha, beta, micro) and the influence of the dose volume distribution was evaluated. Some test examples for 131I and 90Y labeled pharmaceuticals are described to further explain the properties of the F factor and its potential applications. To demonstrate dosimetric feasibility and advantages of the proposed F factor formalism in systemic radiotherapy, we have performed a retrospective planning study on selected patient case. F factor formalism helps to assess the total activity to be administered to the patient taking into account the heterogeneity in activity uptake and dose distribution, giving the same TCP of a homogeneous prescribed dose distribution. Animal studies and collection of standardized clinical data are needed to ascertain the effects of nonuniform dose distributions and to better assess the radiobiological input parameters of the model based on LQ model.

Dose model for stent-based delivery of a radioactive compound for the treatment of restenosis in coronary arteries.

Radiolabeled drug-eluting stents have been proposed recently as a novel method to potentially reduce restenosis in coronary arteries. A P-32 labeled oligonucleotide (ODN) loaded on a polymer coated stent is slowly released in the arterial wall to deliver a therapeutic dose to the target tissue. However, the relatively low proportion of drugs transferred to the arterial wall (<2%-5% typically) raises questions about the degree to which radiolabeled drugs eluted from the stent can contribute to the total radiation dose delivered to tissues. A three-dimensional diffusion-convection transport model is used to model the transport of a hydrophilic drug released from the surface of a stent to the arterial media. Large drug concentration gradients are observed near the stent struts giving rise to a nonuniform radiation activity distribution for the drug in the tissues as a function of time. A voxel-based kernel convolution method is used to calculate the radiation dose rate resulting from this activity build-up in the arterial wall based on the medical internal radiation dose formalism. Measured residence time for the P-32 ODN in the arterial wall and at the stent surface obtained from animal studies are used to normalize the results in terms of absolute dose to tissue. The results indicate that radiation due to drug eluted from the stent contributes only a small fraction of the total radiation delivered to the arterial wall, the main contribution coming from the activity that remains embedded in the stent coating. For hydrophilic compounds with rapid transit times in arterial tissue and minimal binding interactions, the activity build-up in the arterial wall contributes only a small fraction to the total dose delivered by the P-32 ODN stent. For these compounds, it is concluded that radiolabeled drug-eluting stent will not likely improve the performance of radioactive stents for the treatment of restenosis. Also, variability in the delivery efficacy of drug delivery devices makes accurate dosimetry difficult and the drug washout in the systemic circulatory system may yield an unnecessary activity build-up and dose to healthy organs.

Dosimetry of fractionated administration of 125I-labeled antibody at experimental radioimmunotargeting.

Radiotherapy of solid tumors is preferably performed in fractionated doses. Conversely, radioimmunotherapy with nuclide-carrying antibodies delivers a continuously decreasing low dose rate during a longer time period after a single injection. In the current study, the same total amount of 125I-labeled anticytokeratin monoclonal antibody (MoAb) was administrated in one, three, or ten injections and the dosimetry was evaluated. Three groups of nude mice (10 mice each) with HeLa Hep 2 xenografts were injected with 1 x 100 microg/22.2 megabecquerel (MBq), 3 x 33 microg/7.4 MBq, and 10 x 10 microg/2.22 MBq 125I-labeled TS1 MoAb, respectively. The mice were examined scintigraphically over a 54-day period (total number of radio immunoscintigraphies (RISs) = approximately 700) and doses to tumor and normal tissues were estimated according to the medical internal radiation dose formalism. A single bolus injection caused higher tumor uptake, tumor dose, and tumor to nontumor dose ratio than administration of the same total dose of antibody and radioactivity in three or ten separate injections. The single bolus injection caused a tenfold higher tumor uptake (% injected dose, or ID) compared with the group receiving ten injections. This caused a tumor dose of 17 gray to the group receiving a single bolus injection. In this antigen target system, a single injection of a large amount of antibody was found to be more efficient than the same antibody dose subdivided into three or ten fractions. It was concluded that not only the radioactivity but also the amount of antibody per fraction should be considered when determining optimal fractionated radioimmunotherapy.