High-dose (131)I-tositumomab (anti-CD20) radioimmunotherapy for non-Hodgkin's lymphoma: adjusting radiation absorbed dose to actual organ volumes.

Radioimmunotherapy (RIT) using (131)I-tositumomab has been used successfully to treat relapsed or refractory B-cell non-Hodgkin's lymphoma (NHL). Our approach to treatment planning has been to determine limits on radiation absorbed dose to critical nonhematopoietic organs. This study demonstrates the feasibility of using CT to adjust for actual organ volumes in calculating organ-specific absorbed dose estimates. METHODS: Records of 84 patients who underwent biodistribution studies after a trace-labeled infusion of (131)I-tositumomab for RIT (January 1990 and April 2003) were reviewed. Serial planar gamma-camera images and whole-body NaI probe counts were obtained to estimate (131)I-antibody source-organ residence times as recommended by the MIRD Committee. The source-organ residence times for standard man or woman were adjusted by the ratio of the MIRD phantom organ mass to the CT-derived organ mass. RESULTS: The mean radiation absorbed doses (in mGy/MBq) for our data using the MIRD model were lungs = 1.67; liver = 1.03; kidneys = 1.08; spleen = 2.67; and whole body = 0.3; and for CT volume-adjusted organ volumes (in mGy/MBq) were lungs = 1.30; liver = 0.92; kidneys = 0.76; spleen = 1.40; and whole body = 0.22. We determined the following correlation coefficients between the 2 methods for the various organs: lungs, 0.49 (P = 0.0001); liver, 0.64 (P = 0.004); kidneys, 0.45 (P = 0.0004); spleen, 0.22 (P = 0.0001); and whole body, 0.78 (P = 0.0001), for the residence times. For therapy, patients received mean (131)I administered activities of 19.2 GBq (520 mCi) after adjustment for CT-derived organ mass compared with 16.0 GBq (433 mCi) that would otherwise have been given had therapy been based only using standard MIRD organ volumes-a statistically significant difference (P = 0.0001). CONCLUSION: We observed large variations in organ masses among our patients. Our treatments were planned to deliver the maximally tolerated radiation dose to the dose-limiting normal organ. This work provides a simplified method for calculating patient-specific radiation doses by adjusting for the actual organ mass and shows the value of this approach in treatment planning for RIT.     

Primary lung cancer: biodistribution and dosimetry of two In-111- labeled monoclonal antibodies

This study was undertaken to measure the biokinetics and organ dosimetry of indium-111-labeled monoclonal antibodies (MoAbs) with a whole-body gamma camera imaging technique. Twenty patients with primary lung cancer were studied with two different MoAb agents (anti-carcinoembryonic antigen ZCEO25 and antiadenocarcinoma LA20207). Imaging was performed at 1, 24, 72, and 144 hours after injection. Scintigraphic whole-body retention was verified by means of comparison with the results from in vitro counting of excreta. Organ retention was verified in an abdominal phantom. The MoAb cleared slowly from the heart and lungs, the brain and spleen showed no clearance, and the liver showed increased activity over the 6-day period. Dosimetry for ZCE025 showed a dose to the liver of 1.3 rad/mCi (0.36 mGy/MBq); heart, 1.5 rad/mCi (0.40 mGy/MBq); spleen, 1.1 rad/mCi (0.29 mGy/MBq); total body, 0.49 rad/mCi (0.13 mGy/MBq); and testes, 0.39 rad/mCi (0.11 mGy/MBq). The dosimetry for LA20207 was similar.     

Radiation dosimetry of a 99mTc-labeled IgM murine antibody to CD15 antigens on human granulocytes.

99mTc-labeled anti-stage specific embryonic antigen-1 (anti-SSEA-1) is an injectable IgM antibody derived from mice. It binds to CD15 antigens on some granulocytic subpopulations of human white blood cells in vivo after systemic administration. The purpose of this study was to measure biodistribution of 99mTc-labeled anti-SSEA-1 and perform radiation dosimetry in 10 healthy human volunteers. METHODS: Transmission scans and whole-body images were acquired sequentially on a dual-head camera for 32 h after the intravenous administration of about 370 MBq (10.0 mCi) of the radiopharmaceutical. Renal excretion fractions were measured from 10 to 14 discrete urine specimens voided over 27.9 +/- 2.0 h. Multiexponential functions were fit iteratively to the time-activity curves for 17 regions of interest using a nonlinear least squares regression algorithm. The curves were integrated numerically to yield source organ residence times. Gender-specific radiation doses were then estimated individually for each subject, using the MIRD technique, before any results were averaged. RESULTS: Quantification showed that the kidneys excreted 39.5% +/- 6.5% of the administered dose during the first 24 h after administration. Image analysis showed that 10%-14% of the radioactivity went to the spleen, while more than 40% went to the liver. Residence times were longest in the liver (3.37 h), followed by the bone marrow (1.09 h), kidneys (0.84 h) and the spleen (0.65 h). The dose-limiting organ in both men and women was the spleen, which received an average of 0.062 mGy/MBq (0.23 rad/mCi, range 0.08-0.30 rad/mCi), followed by the kidneys (0.051 mGy/MBq), liver (0.048 mGy/MBq) and urinary bladder (0.032 mGy/MBq). The effective dose equivalent was 0.018 mSv/MBq (0.068 rem/mCi). CONCLUSION: The findings suggest that the radiation dosimetry profile for this new infection imaging agent is highly favorable.     

Biodistribution and radiation dosimetry of [N-methyl-11C]mirtazapine, an antidepressant affecting adrenoceptors.

Central adrenoceptors cannot currently be studied by PET neuroimaging due to a lack of appropriate radioligands. The fast-acting antidepressant drug mirtazapine, radiolabelled for PET, may be of value for assessing central adrenoceptors, provided that the radiation dosimetry of the radioligand is acceptable. To obtain that information, serial whole-body images were made for up to 70 min following intravenous injection of 326 and 185 MBq [N-methyl-11C]mirtazapine (specific activities E.O.S. of 119 and 39G Bq/micromol, respectively) in a healthy volunteer. Ten source organs plus remaining body were considered in estimating absorbed radiation doses calculated using MIRD 3.1. The highest absorbed organ doses were found to the lungs (3.4 x 10(-2) mGy/MBq), adrenals (1.2 x 10(-2) mGy/MBq), spleen (1.2 x 10(-2) mGy/MBq), and gallbladder wall (1.1 x 10(-2) mGy/MBq). The effective dose was estimated to be 6.8 x 10(-3) mSv/MBq, which is similar to that produced by several radioligands used routinely for neuroimaging.     

Biodistribution and radiation dosimetry of [<Superscript>123</Superscript>I]ADAM in healthy human subjects: preliminary results

[(123)I]ADAM [2-((2-((dimethylamino)methyl)phenyl)thio)-5-iodophenylamine (ADAM)] has recently been shown to be a very promising imaging ligand for the detection of serotonin transporters (SERT) in human brain, because of its high specificity for SERT. [(123)I]ADAM has previously been used only for animal studies. In this work, we investigated the radiation dosimetry and biodistribution of [(123)I]ADAM based on whole-body scans in healthy human volunteers. Following the administration of 196+/-20 MBq (range 157-220 MBq) [(123)I]ADAM, serial whole-body images were performed up to 24 h. Estimates of radiation absorbed dose were calculated using the MIRDOSE 3.0 program with a dynamic bladder model. Twelve source organs were considered in estimating absorbed radiation doses for organs of the body. The highest absorbed organ doses were found to the lower large intestine wall (8.3.10(-2) mGy/MBq), kidneys (5.2.10(-2) mGy/MBq), urinary bladder wall (4.9.10(-2) mGy/MBq) and thyroid (4.3.10(-2) mGy/MBq). The effective dose was estimated to be 2.2.10(-2) mSv/MBq. The results suggest that [(123)I]ADAM is of potential value as a tracer for single-photon emission tomography imaging of serotonin receptors in humans, with acceptable dosimetry and high brain uptake.     

Radiation dose estimates in humans for (11)C-acetate whole-body PET.

11C-Acetate is currently being investigated as a new tracer for imaging neoplasms, most notably prostate cancer and its metastases. Previously reported dose estimates for (11)C-acetate prepared by the Oak Ridge Institute for Science and Education (ORISE) were based on a simple 3-compartment model in which all activity not measured in blood or excretion via breath was assumed to reside in the heart. Because all organs are involved in acetate metabolism to some extent, these estimates might overestimate heart and underestimate other organ dosimetry. Dynamic whole-body (11)C-acetate PET was therefore performed on 6 healthy human volunteers. Measured dose estimates for all target organs were compared with the existing ORISE values. METHODS: After transmission scanning had been performed for measured attenuation, 525 MBq of (11)C-acetate were injected intravenously, and 5 sequential whole-body emission scans were obtained from the head to mid thighs. Regions of interest were drawn to encompass the entire activity in all visible organs at each time point. Time-activity data were fit in a least-squares sense to obtain residence times. Absorbed dose estimates were determined using MIRDOSE3.1 software. RESULTS: The effective dose was 0.0049 mSv/MBq. The organs receiving the highest absorbed doses were the pancreas (0.017 mGy/MBq), bowel (0.011 mGy/MBq), kidneys (0.0092 mGy/MBq), and spleen (0.0092 mGy/MBq). No urinary excretion of tracer was measurable. CONCLUSION: Using these new estimates for (11)C-acetate dosimetry, the maximum injected activity under Radioactive Drug Research Committee limits can be raised up to 5-fold over the limit imposed by the previous ORISE estimates. A higher injected activity would improve counting statistics and, it is hoped, overall image quality and tumor detection with whole-body (11)C-acetate PET.     

High-dose radioimmunotherapy with 90Y-ibritumomab tiuxetan: comparative dosimetric study for tailored treatment.

High-dose (90)Y-ibritumomab tiuxetan therapy and associated autologous stem cell transplantation (ASCT) were applied after dosimetry. This paper reports dosimetric findings for 3 different methods, including image corrections and actual organ mass corrections. Our first goal was to identify the most reliable and feasible dosimetric method to be adopted in high-dose therapy with (90)Y-ibritumomab tiuxetan. The second goal was to verify the safety of the prescribed activity and the best timing of stem cell reinfusion. METHODS: Twenty-two patients with refractory non-Hodgkin's lymphoma were enrolled into 3 activity groups escalating to 55.5 MBq/kg. A somewhat arbitrary cutoff of 20 Gy to organs (except red marrow) was defined as a safe limit for patient recruitment. ASCT was considered of low risk when the dose to reinfused stem cells was less than 50 mGy. (111)In-Ibritumomab tiuxetan (185 MBq) was administered for dosimetry. Blood samples were collected up to 130 h after injection to derive individual blood clearance rates and red marrow doses. Five whole-body images were acquired up to 7 d after injection. A transmission scan and a low-dose CT scan were also acquired. The conjugate-view technique was used, and images were corrected for background, scatter, and attenuation. Absorbed doses were calculated using the OLINDA/EXM software, adjusting doses for individual organ masses. The biodistribution data were analyzed for dosimetry by the conjugate-view technique using 3 methods. Method A was a patient-specific method applying background, scatter, and attenuation correction, with absorbed doses calculated using the OLINDA/EXM software and doses adjusted for individual organ masses and individually estimated blood volumes. Method B was a reference method using the organ masses of the reference man and woman phantoms. Method C was a simplified method using standard blood and red marrow volumes and no corrections. RESULTS: The medians and ranges (in parentheses) for dose estimates (mGy/MBq) according to method A were 1.7 (0.3-3.5) for lungs, 2.8 (1.8-10.6) for liver, 1.7 (0.6-3.8) for kidneys, 1.9 (0.8-5.0) for spleen, 0.8 (0.4-1.0) for red marrow, and 2.8 (1.3-4.7) for testes. None of patients had to postpone ASCT. Absorbed doses from method B differed from method A by up to 100% for liver, 80% for kidneys, 335% for spleen, and 80% for blood because of differences between standard and actual masses. Compared with method A, method C led to dose overestimates of up to 4-fold for lungs, 2-fold for liver, 5-fold for kidneys, 7-fold for spleen, 2-fold for red marrow, and 2-fold for testes. CONCLUSION: Patient-specific dosimetry with image correction and mass adjustment is recommended in high-dose (90)Y-ibritumomab tiuxetan therapy, for which liver is the dose-limiting organ. Overly simplified dosimetry may provide inaccurate information on the dose to critical organs, the recommended values of administered activity, and the timing of ASCT.     

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.     

18F]fluoroestradiol radiation dosimetry in human PET studies.

[18F]16alpha-fluoroestradiol (FES) is a PET imaging agent useful for the study of estrogen receptors in breast cancer. We estimated the radiation dosimetry for this tracer using data obtained in patient studies. METHODS: Time-dependent tissue concentrations of radioactivity were determined from blood samples and PET images in 49 patients (52 studies) after intravenous injection of FES. Radiation absorbed doses were calculated using the procedures of the MIRD committee, taking into account the variation in dose based on the distribution of activities observed in the individual patients. Effective dose equivalent was calculated using International Commission on Radiological Protection Publication 60 weights for the standard woman. RESULTS: The effective dose equivalent was 0.022 mSv/MBq (80 mrem/mCi). The organ that received the highest dose was the liver (0.13 mGy/MBq [470 mrad/mCi]), followed by the gallbladder (0.10 mGy/MBq [380 mrad/mCi]) and the urinary bladder (0.05 mGy/MBq [190 mrad/mCi]). CONCLUSION: The organ doses are comparable to those associated with other commonly performed nuclear medicine tests. FES is a useful estrogen receptor-imaging agent, and the potential radiation risks associated with this study are well within accepted limits.     

Estimation of internal absorbed dose of l-[methyl-11C]methionine using whole-body positron emission tomography

l-[Methyl-¹¹C]-methionine (¹¹C-methionine) is proposed as a useful radiotracer for tumour diagnosis. Human biodistribution data of cumulated activities and absorbed doses estimated by the MIRD (medical internal radiation dosimetry) method for ¹¹C-methionine are not available in the literature. In this study we measured the organ activity for ¹¹C-methionine by using whole-body positron emission tomography (PET) and estimated the absorbed doses to 25 organs by the MIRD method. Whole-body dynamic PET scans were performed on five normal volunteers to measure the time course of the organ activity concentration (activity/volume) after intravenous administration of ¹¹C-methionine. Cumulated activities of the ten source organs were calculated from the time-activity curves, obtained from the dynamic PET data. Absorbed dose estimates were performed by the MIRD method for the Caucasian reference man and for the Japanese reference man. The organs which received the highest absorbed doses for the Caucasian reference man were found to be the bladder wall (2.7×10^–2 mGy/MBq), the pancreas (1.9×10^–2 mGy/ MBq), the liver (1.8× 10^–2 mGy/MBq) and the kidney (1.1×10^–2 mGy/MBq). The effective doses for the Caucasian reference man and the Japanese reference man were calculated as 5.2×10^–3 and 5.0×10^–3 mSv/MBq, respectively. Received 16 December 1997 and in revised form 30 January 1998     

Whole-body kinetics and dosimetry ofl-3-[123I]iodo-α-methyltyrosine

The synthetic amino acidl-3-[¹²³I]iodo--methyltyrosine (IMT) is currently under clinical evaluation as a single-photon emission tomography (SPET) tracer of amino acid uptake in brain tumours. So far, dosimetric data in respect of IMT are not available. Therefore we investigated the whole-body distribution of IMT in six patients with cerebral gliomas and the radiation doses were estimated. Whole-body scans were acquired at 1.5, 3 and 5 h after i.v. injection of 370–550 MBq IMT. The bladder was voided prior to each scan and the radioactivity excreted in the urine was measured. Based on the MIRD-11 method and the updated MIRDOSE3, the mean absorbed doses for various organs and the effective dose were calculated from geometric means of the anterior and posterior whole-body scans using seven source organs and the residence time. IMT was predominantly excreted by the kidneys (52.8%±11.5% at 1.5 h p.i., 63.0%±15.7% at 3 h p.i. and 74.6%±9.8% at 5 h p.i.). No organ system other than the urinary tract showed significant retention of the tracer. Early whole-body scans revealed slightly increased tracer uptake in the liver and in the bowel. Highest absorbed doses were found for the urinary bladder wall (0.047 mGy/MBq), the kidneys (0.010 mGy/MBq), the lower large intestinal wall (0.011 mGy/MBq) and the upper large intestinal wall (0.008 mGy/MBq). The effective dose according to ICRP 60 was estimated to be 0.0073 mSv/MBq for adults. This leads to an effective dose of 3.65 mSv in a typical brain SPET study using 500 MBq IMT. The MIRDOSE3 scheme yielded similar results. Thus, in spite of the relatively high tracer dose required for optimal brain scanning, radiation exposure in SPET studies with IMT is in the normal range of routine nuclear medicine investigations.     

Biodistribution and imaging with (123)I-ADAM: a serotonin transporter imaging agent.

2-((2-((Dimethylamino)methyl)phenyl)thio)-5-(123)I-iodophenylamine ((123)I-ADAM) is a new radiopharmaceutical that selectively binds the central nervous system serotonin transporters. The purpose of this study was to measure its whole-body biokinetics and estimate its radiation dosimetry in healthy human volunteers. The study was conducted within a regulatory framework that required its pharmacologic safety to be assessed simultaneously. METHODS: The sample included 7 subjects ranging in age from 22 to 54 y old. An average of 12.7 whole-body scans were acquired sequentially on a dual-head camera for up to 50 h after the intravenous administration of 185 MBq (5 mCi) (123)I-ADAM. The fraction of the administered dose in 13 regions of interest (ROIs) was quantified from the attenuation-corrected geometric mean counts in conjugate views. Multiexponential functions were iteratively fit to each time-activity curve using a nonlinear, least-squares regression algorithm. These curves were numerically integrated to yield source organ residence times. Gender-specific radiation doses were then estimated with the MIRD technique. SPECT brain scans obtained 3 h after injection were evaluated using an ROI analysis to determine the range of values for the region to cerebellum. RESULTS: There were no pharmacologic effects of the radiotracer on any of the subjects, including no change in heart rate, blood pressure, or laboratory results. Early planar images showed differentially increased activity in the lungs. SPECT images demonstrated that the radiopharmaceutical localized in the midbrain in a distribution that is consistent with selective transporter binding. The dose-limiting organ in both men and women was the distal colon, which received an average of 0.12 mGy/MBq (0.43 rad/mCi) (range, 0.098-0.15 mGy/MBq). The effective dose equivalent and effective dose for (123)I-ADAM were 0.037 +/- 0.003 mSv/MBq and 0.036 +/- 0.003 mSv/MBq, respectively. The mean adult male value of effective dose for (123)I-ADAM is similar in magnitude to that of (111)In-diethylenetriaminepentaacetic acid (0.035 mGy/MBq), half that of (111)In-pentetreotide (0.81 mGy/MBq), and approximately twice that of (123)I-inosine 5'-monophosphate (0.018 mGy/MBq). The differences in results between this study and a previous publication are most likely due to several factors, the most prominent being this dataset used attenuation correction of the scintigraphic data. Region-to-cerebellum ratios for the brain SPECT scans were 1.95 +/- 0.13 for the midbrain, 1.27 +/- 0.10 for the medial temporal regions, and 1.11 +/- 0.07 for the striatum. CONCLUSION: (123)I-ADAM may be a safe and effective radiotracer for imaging serotonin transporters in the brain and the body.     

Radioimmunotherapy of non-Hodgkin's lymphoma with 90Y-DOTA humanized anti-CD22 IgG (90Y-Epratuzumab): do tumor targeting and dosimetry predict therapeutic response?

A DOTA (1,4,7,10-tetraazacyclododecane-N,N',N",N"'-tetraacetic acid)-conjugated, (111)In- and (90)Y-labeled humanized antibody to CD22, epratuzumab, was studied in patients with non-Hodgkin's lymphoma (NHL) to assess biodistribution and tumor targeting, pharmacokinetics, dosimetry, and anti-antibody response. Of particular interest was to evaluate whether pretherapy targeting and tumor dosimetry could predict therapeutic responses. METHODS: Patients received a pretherapy imaging study with (111)In-DOTA-epratuzumab IgG (0.75 mg/kg), followed about 1 wk later with (90)Y-DOTA-epratuzumab starting at a dose level of 0.185 GBq/m(2) (5 mCi/m(2)) in patients who had prior high-dose chemotherapy (group 2), and at 0.370 GBq/m(2) in patients who did not have a prior transplant (group 1), with escalation in 0.185-GBq/m(2) increments. RESULTS: The effective blood half-life for (111)In-DOTA epratuzumab was 36.1 +/- 7.9 h (n = 25) compared with 35.2 +/- 7.0 h for (90)Y-DOTA-epratuzumab (n = 22). The whole-body half-life for (90)Y-DOTA-epratuzumab estimated from (111)In-DOTA-epratuzumab scintigraphy was 58.3 +/- 4.7 h (n = 20), with urine collection confirming the loss of between 2.2% and 15.9% of the injected activity over 3 d (n = 3). One-hundred sixteen of 165 CT-confirmed lesions were visualized with (111)In-DOTA-epratuzumab. Radiation-absorbed doses to liver, lungs, and kidneys averaged 0.55 +/- 0.13 (n = 17), 0.28 +/- 0.06 (n = 17), and 0.38 +/- 0.07 mGy/MBq (n = 10), respectively, with 0.14 +/- 0.02 and 0.23 +/- 0.04 mGy/MBq delivered to the whole-body and red marrow, respectively. Tumor doses (n = 14 lesions in 10 patients) ranged from 1.0 to as much as 83 mGy/MBq for a 0.5-g lesion (median, 7.15 mGy/MBq). Group 2 patients were more likely to experience significant hematologic toxicities, but doses of up to 0.370 GBq/m(2) of (90)Y-DOTA-epratuzumab were tolerated with standard support measures, whereas patients in group 1 tolerated doses of up to 0.740 GBq/m(2) with the potential for further escalation. Anti-tumor effects were seen in both indolent and aggressive NHL. The data also suggest that anti-tumor responses of potentially equal magnitude can occur irrespective of tumor targeting and tumor size. Hence, tumor response did not correlate with the radiation dose delivered or with the tumor being visualized by external imaging. An anti-antibody response to epratuzumab was detected by an enzyme-linked immunosorbent assay in only 2 of 16 patients. CONCLUSION: These results suggest that (90)Y-DOTA-epratuzmab is a promising agent for the treatment of NHL and warrants further study. There was evidence suggesting that in this system, factors other than tumor radiation dose and targeting may be involved in the success of radioimmunotherapy.     

Dosimetry of 60/61/62/64Cu-ATSM: a hypoxia imaging agent for PET

Purpose Cu-diacetyl-bis(N⁴-methylthiosemicarbazone (Cu-ATSM) is an effective marker for the delineation of hypoxic tissue. Dosimetry calculations by the established Medical Internal Radionuclide Dose (MIRD) approach were performed with both animal and patient data.Methods Human absorbed dose estimates extrapolated from rat data were based on the biodistribution of ⁶¹Cu-ATSM in adult rats. Eighteen tissues were harvested and time–activity curves generated. The measured residence times and the MIRD S-values for ⁶⁰Cu-ATSM were used to estimate human absorbed doses. The biodistribution of the tracer was directly measured in five patients injected with approximately 480 MBq of ⁶⁰Cu-ATSM and imaged by positron emission tomography (PET) with a whole-body protocol. The combined data from all patients were used to derive organ residence times, and organ doses were calculated by MIRD methodology for ⁶⁰Cu-ATSM, ⁶¹Cu-ATSM, ⁶²Cu-ATSM, and ⁶⁴Cu-ATSM.Results Human absorbed dose estimates extrapolated from rat biodistribution data indicated that the kidneys appeared to be the dose-limiting organ (0.083 mGy/MBq) with a whole-body dose of 0.009 mGy/MBq. Based on the human PET imaging data, the liver appeared as the dose-limiting organ, with an average radiation dose of 0.064 mGy/MBq. The whole-body dose was 0.009 mGy/MBq and the effective dose was 0.011 mSv/MBq.Conclusion These relatively small absorbed doses to normal organs allow for the safe injection of 500–800 MBq of ⁶⁰Cu-ATSM, which is sufficient for PET imaging in clinical trials.     

Safety, biodistribution, and dosimetry of 123I-IMPY: a novel amyloid plaque-imaging agent for the diagnosis of Alzheimer's disease.

(123)I-IMPY (6-iodo-2-(4'-dimethylamino-)phenyl-imidazo[1,2-a]pyridine) is a novel radiopharmaceutical that selectively binds to Alzheimer's disease (AD) amyloid plaques. As a first step toward validating this radiopharmaceutical as an imaging biomarker for AD, we measured the whole-body biokinetics and radiation dosimetry of (123)I-IMPY in AD patients and cognitively normal control subjects. The pharmacologic safety profile of the compound was simultaneously assessed. METHODS: The sample included 9 subjects ranging in age from 44 to 80 y. Whole-body images were obtained for each subject (mean +/- SD, 9.0 +/- 3.2 scans per subject) for up to 48 h after the intravenous administration of 185 MBq (5 mCi) of (123)I-IMPY. The fraction of administered activity in 12 regions of interest was quantified from the attenuation-corrected geometric mean counts in conjugate views. Multiexponential functions were iteratively fit to each time-activity curve using a nonlinear, least-squares regression algorithm. These curves were numerically integrated to yield cumulated activity values for source organs. Radiation doses were then estimated with the MIRD technique. RESULTS: The radiotracer had no pharmacologic effects (produced no changes in heart rate, blood pressure, or laboratory results) on any of the subjects. Radiation dosimetry estimates indicated that the dose-limiting organ was the gallbladder, which received an average of 0.135 mGy/MBq (range, 0.075-0.198 mGy/MBq). The effective dose equivalent and effective dose for (123)I-IMPY were 0.042 +/- 0.003 mSv/MBq and 0.035 +/- 0.001 mSv/MBq, respectively. The mean effective dose for (123)I-IMPY was similar to that for (111)In-diethylenetriaminepentaacetic acid (0.035 mGy/MBq), less than half that for (111)In-pentetreotide (0.81 mGy/MBq), and approximately twice that for (123)I-IMP (0.018 mGy/MBq). No significant differences were found between men and women or between AD patients and control subjects. CONCLUSION: (123)I-IMPY may be a safe radiotracer with appropriate biokinetics for imaging amyloid plaques in AD patients.     

Estimation of absorbed doses in humans due to intravenous administration of fluorine-18-fluorodeoxyglucose in PET studies

Radiation absorbed doses due to intravenous administration of fluorine-18-fluorodeoxyglucose in positron emission tomography (PET) studies were estimated in normal volunteers. The time-activity curves were obtained for seven human organs (brain, heart, kidney, liver, lung, pancreas, and spleen) by using dynamic PET scans and for bladder content by using a single detector. These time-activity curves were used for the calculation of the cumulative activity in these organs. Absorbed doses were calculated by the MIRD method using the absorbed dose per unit of cumulated activity, "S" value, transformed for the Japanese physique and the organ masses of the Japanese reference man. The bladder wall and the heart were the organs receiving higher doses of 1.2 x 10(-1) and 4.5 x 10(-2) mGy/MBq, respectively. The brain received a dose of 2.9 x 10(-2) mGy/MBq, and other organs received doses between 1.0 x 10(-2) and 3.0 x 10(-2) mGy/MBq. The effective dose equivalent was estimated to be 2.4 x 10(-2) mSv/MBq. These results were comparable to values of absorbed doses reported by other authors on the radiation dosimetry of this radiopharmaceutical.     

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

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.     

Biodistribution and kinetics of (131)I-labelled anti-CD20 MAB IDEC-C2B8 (rituximab) in relapsed non-Hodgkin's lymphoma

The native chimeric human-mouse anti-CD20 antibody IDEC-C2B8 (rituximab) is therapeutically applied in relapsed non-Hodgkin's lymphoma (NHL). The purpose of this study was to evaluate the distribution and pharmacokinetics of iodine-131 labelled rituximab in humans for radioimmunotherapy of relapsed CD20-positive NHL. Thirty-five patients with relapsed NHL were administered 20-40 mg rituximab labelled with 250 MBq (131)I. Biodistribution was determined by the gamma camera whole-body scans, whole-body probe measurements and the analysis of serial blood and urine samples. Dosimetry was performed using the MIRDOSE 3 program. Antibody administration was well tolerated. The whole-body activity showed a mono-exponential decrease with a wide range of effective half-lives, the mean value (88 h) being significantly longer than the half-life of its murine counterpart, tositumomab. This led to appropriately higher dose factors for the whole body and organs. Activity was excreted mainly through the kidneys. Normal organs showed decreasing ratios of organ to whole-body activity over time, whereas the tumour tissue presented different kinetics, with increasing ratios of tumour to whole-body activity as evidence for specific antibody binding. It is concluded that (131)I-labelled rituximab is suitable for pretherapeutic dosimetry. Due to the wide range of whole-body and organ dose factors, individual dosimetry is necessary for radioimmunotherapy with (131)I-labelled rituximab. The therapeutic activities of (131)I-labelled rituximab required to deliver similar doses should be lower than those of its murine counterpart.     

18F-Fluorothymidine radiation dosimetry in human PET imaging studies.

3'-Deoxy-3'-(18)F-fluorothymidine ((18)F-FLT) is a PET imaging agent that shows promise for studying cellular proliferation in human cancers. FLT is a nucleoside analog that enters cells and is phosphorylated by human thymidine kinase 1, but the 3' substitution prevents further incorporation into DNA. We estimated the radiation dosimetry for this tracer from data gathered in patient studies. METHODS: Time-dependent tissue concentrations of radioactivity were determined from blood samples and PET images of 18 patients after intravenous injection of (18)F-FLT. Radiation-absorbed doses were calculated using the MIRD Committee methods, taking into account variations that were based on the distribution of activities observed in the individual patients. Effective dose equivalent (EDE) was calculated using International Commission on Radiological Protection Publication 60 tissue weighting factors for the standard man and woman. RESULTS: For a single bladder voiding at 6 h after (18)F-FLT injection, the (18)F-FLT EDE (mean +/- SD) was 0.028 +/- 0.012 mSv/MBq (103 +/- 43 mrem/mCi) for a standard male patient and 0.033 +/- 0.012 mSv/MBq (121 +/- 43 mrem/mCi) for a standard female patient. The organ that received the highest dose was the bladder (male, 0.179 mGy/MBq [662 mrad/mCi]; female, 0.174 mGy/MBq [646 mrad/mCi]), followed by the liver (male, 0.045 mGy/MBq [167 mrad/mCi]; female, 0.064 mGy/MBq [238 mrad/mCi]), the kidneys (male, 0.035 mGy/MBq [131 mrad/mCi]; female, 0.042 mGy/MBq [155 mrad/mCi]), and the bone marrow (male, 0.024 mGy/MBq [89 mrad/mCi]; female, 0.033 mGy/MBq [122 mrad/mCi]). CONCLUSION: Organ dose estimates for (18)F-FLT are comparable to those associated with other commonly performed nuclear medicine tests, and the potential radiation risks associated with (18)F-FLT PET imaging are within accepted limits.     

Biodistribution and radiation dosimetry of 11C-WAY100,635 in humans.

Serotonin 1A receptors have been implicated in a variety of conditions including depression, suicidal behavior, and aggression. Dose estimates for current human studies are based on data from rat dosimetry studies. We report the biodistribution and dosimetry of the PET serotonin 1A antagonist 11C-WAY100,635 in humans. METHODS: PET studies of 6 healthy human volunteers (3 male, 3 female) were acquired after a bolus injection of 11C-WAY100,635. Transmission scans of 3.5 min were obtained at each bed position before injection, and emission scans then were collected in 2-dimensional mode over 8 bed positions. Regions of interest were drawn around the brain, left and right lungs, heart, liver, stomach wall, gallbladder, left and right kidneys, spleen, and urinary bladder. Because no fluid was removed from the subjects, whole-body radioactivity was calculated using the injected dose and a calibration factor determined from a cylinder phantom. The area under the curve for each region of interest was determined by trapezoidal integration of the first 3 points, with subsequent points fit by a decreasing monoexponential. The area under the curve was then divided by counts in the whole body, and the resulting residence times were entered into the MIRDOSE3 program. RESULTS: Primary elimination was via kidneys to the urinary bladder. There were no sex differences in organ residence times. The urinary bladder wall was the organ with the highest estimated radiation dose (1.94 x 10(-1) +/- 3.57 x 10(-2) mGy/MBq). Except for the kidney and bladder wall, correlation was good between human dosimetry estimates and estimates reported previously from rats. The human dosimetry was 6.6 and 60.6 times higher in the kidneys and urinary bladder wall, respectively, than estimates from rats. CONCLUSION: The urinary bladder wall is the critical organ for 11C-WAY100,635 in humans. In the United States, according to Radioactive Drug Research Committee guidelines a single dose cannot exceed 300 MBq in a man and 227 MBq in a woman, with up to 3 such injections permitted per annum.