Journal of Medical Physics
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 Table of Contents    
Year : 2012  |  Volume : 37  |  Issue : 4  |  Page : 226-234

Evaluation and comparison of human absorbed dose of 90 Y-DOTA-Cetuximab in various age groups based on distribution data in rats

1 Department of Medical Radiation Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
2 Radiopharmaceutical Research and Development Lab, Nuclear Science and Technology Research Institute, Tehran, Iran
3 Biomedical Physics and Engineering, Tehran University of Medical Sciences, Tehran, Iran
4 Faculty of science, K. N Toosi University of Technology, Tehran, Iran

Date of Submission28-Apr-2012
Date of Decision11-Aug-2012
Date of Acceptance10-Oct-2012
Date of Web Publication20-Nov-2012

Correspondence Address:
Ariandokht Vakili
Department of Medical Radiation Engineering, Science and Research Branch, Islamic Azad University, Tehran
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Source of Support: None, Conflict of Interest: None

DOI: 10.4103/0971-6203.103609

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The organ radiation-absorbed doses have been evaluated for humans in six age groups and both genders based on animal data. After intravenous administration of 90 Y-DOTA-Cetuximab to five groups of rats, they were sacrificed at exact time intervals (2, 24, 48, 72, and 96 h) and the percentage of injected dose per gram of each organ was calculated by direct counting from rat data. By using the formulation that Medical Internal Radiation Dose suggests, radiation-absorbed doses for all organs were calculated and extrapolated from rat to human. The total body absorbed dose for all groups was >22 mGy due to pure β-emission of the applied radiopharmaceutical. The effective dose resulting from an intravenously injected activity of 100 MBq is 56.7 mSv for a 60-kg female adult and 60.3 mSv for a 73-kg male adult. The results demonstrated the usefulness of this method for estimation of β-absorbed dose in humans.

Keywords: Absorbed dose, beta-particles, internal dosimetry, Yttrium-90

How to cite this article:
Vakili A, Jalilian AR, Moghadam AK, Ghazi-Zahedi M, Salimi B. Evaluation and comparison of human absorbed dose of 90 Y-DOTA-Cetuximab in various age groups based on distribution data in rats. J Med Phys 2012;37:226-34

How to cite this URL:
Vakili A, Jalilian AR, Moghadam AK, Ghazi-Zahedi M, Salimi B. Evaluation and comparison of human absorbed dose of 90 Y-DOTA-Cetuximab in various age groups based on distribution data in rats. J Med Phys [serial online] 2012 [cited 2021 Apr 11];37:226-34. Available from:

   Introduction Top

Absorbed-dose calculations provide a scientific basis for evaluating the biologic effects associated with administered radiopharmaceuticals. In cancer therapy, radiation dosimetry supports treatment planning, dose-response analyses, predictions of therapy effectiveness, and completeness of patient medical records. Prediction of human absorbed dose based on animal studies provides valuable distribution data for evaluating the potential use of new radiotracers. Yttrium-90 is a pure β-emitter, so performing dosimetry studies is not possible by using single-photon emission tomography (SPECT) and/or positron emission tomography (PET).

According to the authors' recent project on the production and evaluation of antibodies labeled with therapeutic radioisotopes for radio immune theraphy (RIT) applications, the production of 90 Y-DOTA-Cetuximab was performed.

The use of radiolabeled monoclonal antibodies for the treatment of cancer necessitates the development of dosing schedules that minimize the exposure of healthy tissues to radiation while maximizing the radiation dose received by the tumor. [1] The goal of RIT is to deliver radiation in discrete amounts to tumor sites via a radionuclide that has been conjugated to an antitumor monoclonal antibody (mAb). 90 Y-Cetuximab is a 90 Y-labeled mAb that binds specifically to the extracellular domain of epidermal growth factor receptor (EGFR) on both normal and tumor cells, and competitively inhibits the binding of epidermal growth factor (EGF) and other ligands, such as transforming growth factor-alpha. Binding of Cetuximab to the EGFR blocks phosphorylation and activation of receptor-associated kinesis, resulting in inhibition of cell growth, induction of apoptosis, and decreased matrix metalloproteinase and vascular endothelial growth factor production, resulting in localization of mAb to tumor sites where 90 Y emits β-radiation capable of killing cells adjacent to the target cell. [2],[3] 90 Y is a good candidate for RIT. Its high incidence of β-emission optimizes the dose deposition within the targeted cells while its low incidence of photons emission minimizes the dose received by other organs. [4] It can be produced easily by an 90 Sr/ 90 Y generator, decays by emission of β-radiation with a maximum energy of 2.28 MeV to stable Zirconium-90, with a half-life of 64.1 h. [5],[6],[7]

In this work, a precise description of organ distribution has been used owing to a large amount of distribution data (source organs in dosimetry calculations); the human absorbed radiation dose was estimated based on distribution data for normal rats.

   Materials and Methods Top

DOTA-mono-N-hydroxysuccinimide ester (DOTA-mono-NHS ester) was purchased from Macrocyclics. Amicon Ultera-15 filter (Millipore, MWCO 30000) was purchased from GE Healthcare Inc, Amersham place, Buckinghamshire, UK. All other chemicals were purchased from Aldrich Chemical Co, Gillingham, UK. Cetuximab was kindly provided by Merck Inc, Darmstadt, Germany. Radio-chromatography was performed by counting of Whatman No.1 using a thin-layer chromatography scanner, Bioscan AR2000, Paris, France. Animal studies were carried out in accordance with the United Kingdom Biological Council's Guidelines on the Use of Living Animals in Scientific Investigations, 2 nd ed. All of the rats were male NMRI purchased from Pasteur Institute of Iran; in each group/interval, five rats, before being sacrificed, were kept at routine day/night light program and were kept under common rodent diet pellets. The animal tissue samples were counted using a Wallac 1220 Quantulus, Perkin Elmer, Ultra low-level liquid scintillation spectrometer, Turku, Finland, after sample preparation method instructed by the manufacturer.

90 Y (valence, +3) is obtained from the natural decay of its parent, 90 Sr (t 1 / 2 , 28 years), which is in turn a product of 235 U fission in a nuclear reactor. 90 Y is separated radiochemically from 90 Sr using a series of precipitation and filtration steps [8] or using a series of strontium-selective chromatographic columns. 90 Y was produced by 90 Y/ 90 Sr generator developed at Nuclear Science and Technology Research Institute of Atomic Energy Organization of Iran.

Preparation of 90Y-DOTA-Cetuximab

mAb labeling with 90 Y was achieved starting with chelate DOTA-NHS-ester as described previously. The antibody conjugate was labeled using an optimization protocol according to the literature reports. [9],[10] Radiolabeling of DOTA-cetuximab with 90 Y was performed by adding approximately 1 mg of the conjugate to 37-74 MBq (1-2 mCi) of 90 YCl 3 in 0.1 M ammonium acetate buffer, pH 5.5, followed by 24 h incubation at 37°C. The radiochemical purity of the resulting 90 Y-DOTA-cetuximab was determined by radio-thin-layer chromatography (RTLC). RTLC showed a radiochemical purity more than 92% (specific activity = 0.55 GBq/mg) followed by filtration through PD10 column. The stability of the radioconjugate was tested in the presence of human serum at 37 o C.

Biodistribution studies of radiopharmaceutical

The distribution of 90 Y-DOTA-Cetuximab among tissues was determined in five groups of male normal rats. A volume of 0.1 ml of final 90 Y-DOTA-Cetuximab solution containing 3.7 MBq radioactivity (0.1-0.2 mg/ml IgG determined by UV spectrophotometric method) was injected into the dorsal tail vein. The animals were sacrificed by CO 2 asphyxiation (after anesthesia induction using propofol/xylazine mixture) at the exact time intervals (2, 24, 48, 72, and 96 h), and dissection was started by drawing blood from the aorta, followed by collecting heart, spleen, kidneys, liver, intestine, stomach, and skin samples.

Uptake measurement and analysis of animal data

In order to estimate the human absorbed dose, the initial step involves activity calculation. Consequently, the total amount of radioactivity injected into each rat was measured by counting the 1-ml syringe before and after injection in a dose calibrator with a fixed geometry. The samples were weighed and tissue uptakes were calculated as the percentage of injected dose per gram (%ID/g = %IA/g) by using a beta-scintillator detector. These measurements were tabulated as decay-corrected biodistributions in various organs and at a number of time points after injection of the radiolabeled material. All the organ activity measurements were normalized to the injected activity [Table 1]. The 90 Y activity concentration at time t, C tissue (t), was then calculated as the percentage of injected activity per gram of tissue (%IA/g) with equation (1):
Table 1: Biodistribution of 90Y-DOTA-Cetuximab in normal rats 2-96 h post-injection

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where A tissue (t) is the 90 Y activity in the sample, M tissue is the mass of the sample, and A total is the total activity of 90 Y injected into the rat. The dosimetry estimates were based on a rat distribution study and the calculations were done in accordance with International Commission on Radiation Protection (ICRP) 103 [11] and ICRP 106 [12] recommendations.

To estimate the absorbed dose in human from the biokinetic results in the rat, we used a mass correction factor to account for the different ratios of organ to total body weights in the rat and in human. To first order, we assume that the uptake in a given organ, in %IA, depends only on the ratio of organ mass divided by the total body mass. [13] . To correct for differences in this apportionment ratio between rat and human species, we can use equation (2), where:

This process is essentially an organ correction factor (CR) for differences in relative perfusion between the rat (and other animal) model and the human subject. Usually the biokinetic data from the animals are provided as %IA/g, which simplifies this conversion for dose estimation as the rat organ mass is included in the data set. These correction factors have been calculated by using data that are derived from ICRP and Medical Internal Radiation Dose (MIRD) pamphlet for six age groups and both genders [14] [Table 2] and [Table 3], so are often sizeable and should be applied when using animal data to predict human results.
Table 2: Standard masses (kg) according to ICRP 89[24] and mass correction factors

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Table 3: Organs masses (g) according to ICRP 89[22]

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Dose estimation in humans from rats' biodistribution data

The activity and concentration of the radiopharmaceutical in all major source organs and spaces in the body must be determined for the dose calculation step. Activity calculation was performed by using a mathematical biodistribution model which generated non-decay corrected time activity curves for the source organs including blood, lungs, kidneys, spleen, liver, bone, muscle, skin, and stomach for all groups. For each organ, there is a plot of the distribution data which in points fit to a single exponential equation except for the heart and blood (because it was multi-exponential), by least-squares linear regression that presenting the subtraction between input rate and output rate of radiopharmaceutical to individual organs, fitted a mono-exponential curve. The data points representing the percentage-injected dose (%ID/organ) were created and fitted to a mono-exponential, a bi-exponential, or an uptake-and-clearance curve. The cumulated source activity (A h ) is calculated for each organ according to equation (3) which is presented in the Medical Internal Radiation Dose (MIRD) No. 11: [15]

The activities were determined by integration of mathematical equations that were obtained based on %ID/g for each organ during interval times from 2 to 96 h [Table 4]. [16] The rat data were assumed to approximate the biokinetics in human.
Table 4: Distribution of 90Y-DOTA-Cetuximab during 96 h for humans (MBq.s)

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A fundamental equality generally assumed in the estimation of organ doses is the familiar equation (4):

where S ts is a rectangular matrix giving the dose to a target organ t per unit time activity in a source organ S.[16],[17] Conceptually, equation (4) separates the analytic process into two segments. Given the radionuclide, S refers purely to geometric factors. The cumulated activity Γ h is the area under the curve of activity (A S) versus time. Traditional dimensions, rad/(μCi-h) for S, are changed to cGy/MBq-h for SI units. Notice that D and Γ are column vectors in this formula; their various elements refer to the source and target organs for a specified radionuclide.

Properties of the S matrix

One may logically separate S factor into S np and S p parts; these refer to so-called non-penetrating (np) and penetrating (p) radiation given off by the radionuclide of interest. Typically, the user assigns charged particle radiation to the former category and gamma and X-rays to the latter. Some emitters, such as 90 Y that were used in this work, are purely of the charged-particle type; these are of considerable interest in RIT due to the reduction in ambient radiation levels during therapy procedures, so S np is the only part of S factor for this radioisotope [18] (equation (5):

When all dimensions of an organ t greatly exceed the rang of the electron, i.e., the source and target organ are the same, equation (6)

is assumed to hold, where m is the mass of target organ. The source and target organ are well separated,

The exceptions to the above general rules for bone, marrow, and organ with walls are thoroughly discussed, and the precise values of S factors are presented in tables of the MIRD pamphlet No. 11 [15] for over 110 radionuclides like 90 Y. Methods used for calculation of radiation-absorbed dose to the human normal organs and whole body are by those recommended by the MIRD Committee of the Society of Nuclear Medicine. [19],[20],[21]

   Results Top

Biodistribution of 90 Y-DOTA-cetuximab in rats at five different time intervals, 2, 24, 48, 72, and 96 h, post-injection are shown in [Table 1]. At 2 h post-injection, the activity is mainly in the blood, which is in agreement with the other reported labeled antibodies, such as 64 Cu-DOTA-Cetuximab, [7] 89 Zr-Cetuximab, [22] and 177 Lu-Cetuximab. [23] But the activity of the stomach, muscle, and intestine is rather low. But retention of radiopharmaceutical in the blood at all five time interval was significantly higher in our system indicating the long circulation lifetime of the antibody. High uptake in the lung, blood, and spleen which have EGFR expression was observed. Lung activity concentration was 1.18 ± 0.005 injected dose per gram-ID g/1% at 72 h and 1.23 ± 0.004 at 96 h post-injection, demonstrating the high EGFR expression. The liver also had prominent radioactivity accumulation, with an uptake of 2.19 ± 0.002 ID/g% at 24 h post-injection [Table 1].

The more conservative assumption that, it seems all 90 Y-DOTA-Cetuximab leaves the body due to natural decays would have been too conservative for organs with rapid clearance, such as the brain, kidney, skin, and muscle. Time-activity curves without decay correction are shown in [Figure 1].
Figure 1: The non-decay corrected clearance curves from each organ of the rats (%ID/g, percentage of injected dose per gram) Mass correction factors were calculated in accordance with the MIRD committee of the Society of Nuclear Medicine and the ICRP recommendations for six age groups and both genders, and the mass of a normal rat was considered 0.28 kg, are presented in Table 2

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The radiation-absorbed organ doses estimated in humans according to the biological data from the rat study are shown in [Table 5].
Table 5: Organ dose (mGy) and effective dose (mSv)

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A 100 MBq (2.5 mCi) injection of 90 Y-DOTA-Cetuximab into the human body might result in an estimated absorbed dose of 16.08 mGy for the total body of adult female, 17.32 mGy for adult male, 16.323 mGy for 15-year-old female, 16.956 mGy for 15-year-old male, 17.54 mGy for age 10 years, 17.67 mGy for age 5 years, 18.84 mGy for age 1 year, and 21 mGy for newborn, and the highest absorbed dose was in the liver for all groups, followed by the lungs, kidney, marrow, bone, and skin, which are shown in [Table 5].

The radiation-absorbed dose to red marrow was estimated according to MIRD recommendation and using equations (8 and 9). Three source organs are generally assumed for estimating marrow dose in red marrow, bone, and residual body. [19]

Bone as a source organ consists of two parts, trabecular bone and cortical bone. [14] In order to estimate marrow dose, one can use the blood concentration curve as a surrogate for the marrow concentration curve. [25] Instead of a direct correspondence, the marrow Γ value is set equal to a fraction (f) of the blood curves Γ: [19]

Physically, this relationship is an attempt to correct, to the lowest order, for the mass difference between the whole blood and red marrow. Values for the f factor have been estimated to lie between 0.2 and 0.4; a most probable value of 0.34-0.36 has been determined by Sgouros. [26]

The estimated effective doses to the whole body of all groups resulting from an intravenously injected activity of 100 MBq are presented in [Table 5], the calculations were made in accordance with MIRD/ICRP 106 recommendations. [27]

It is worth mentioning that the radiation-absorbed dose to the red marrow of the rats is significantly high in comparison with other organs. (Calculations were performed using Macey et al.'s report, 1995.) [28] Therefore, it is necessary to attend to the marrow dose in each treatment planning based on RIT.

Comparison of the absorbed dose organs among the six age groups is presented in [Figure 2]. Also, a similar comparison is performed for both genders, which is shown in [Figure 3].
Figure 2: Comparison of absorbed dose among the six age groups: (a) liver, (b) bone, (c) kidney

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Figure 3: Comparison of absorbed dose between two genders: (a) liver, (b) kidney, (c) muscle

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   Discussion Top

Recent trends in radionuclide therapy with radiolabeled antibodies and bone-seeking radiopharmaceuticals have promoted renewed interest in providing more accurate radiation-absorbed dose estimates. A wide range of radionuclides attached to a variety of targeting agents have been used in these trials. For many protocols, radiation-absorbed dose estimates are relied on to decide whether a patient should proceed to therapy and for prescribing the amount of activity that should be administered. The motivation for this work is the provision of absorbed dose estimates for individual patients within the limitations of methodology. Although the S values recommended by ICRP 62 [29] and MIRD Pamphlet 11 [15] have been used to provide the framework for radiation-absorbed dose estimates for human base on distribution data from small animals such as rats, more accurate methods are required for radionuclide therapy procedures. In this investigation, biodistribution of radioimmunoconjugate in rat model showed that it was mostly accumulated in lungs, which were the major organs of accumulation entirely in the study, as shown in [Table 1]. This is in agreement with the previous reports. [30] The lung to blood activity concentration ratio was about 1.68 at 72 h and up to 3.15 at 96 h post-injection. The lungs to muscle ratios were more than 30 at 72 and 96 h post-injection.

The present study estimated the dosimetry of 90 Y-DOTA-Cetuximab based on the generation of a mathematical biodistribution model. In radiological physics, a model of animal is required in the estimation of absorbed radiation dose. This follows from the need to perform integration of normal organ curves out to many physical half-lives. By using only physical decay or some crude form of extrapolation from the last data point(s), the investigator does not effectively understand the long-term course of the data. The same difficulty holds for the estimation of activity values between data points as taken (i.e., the model also provides better interpolation). As the physiological model, one may consider a separate multi-exponential representation for each of the various blood and normal organs. In this open model strategy, there is no explicit relationship between the various sets of exponentials from one organ to another as these fitting processes go on in isolation. This type of solution has certain justification as Laplace Transform analysis shows that linear modeling leads to a set of linear differential equations whose solutions are indeed combinations of various exponential functions. [31] In practice, it may be difficult, however, to fit more than two exponential functions to any organ curve. For one thing, only a single exponential solution is unique. Solutions involving multiple exponential functions have different results depending upon the starting conditions for the modeling algorithm used.

Residence time were calculated using animal and human data, and distribution of ratio of the animal results to human results were constructed for each extrapolation method, in this study, relative organ mass extrapolation method were used from overall four methods which represented by Sparks et al. [13] Relative organ mass scaling is based on the assumption that the uptake of activity in human organs is related to uptake in animal organs by a function of total body mass fractions of the organs in animals and human. [23] As a result of time points deficiency, relative organ mass extrapolation is more precise than physiological time extrapolation for this radiotracer.

The amount of radiation-absorbed dose in a human was calculated by determining the distribution in rats, obtaining the accumulated activity value by integration of multi-exponential mathematical model to each organ, multiplying by the ratio of organs to extrapolate to humans (using relative organ mass extrapolation), and then multiplying the converted rats' cumulative activity to the S factor table of 90 Y. [24] This procedure was also performed for all six age groups and both genders. The highest radiation-absorbed doses per unit-administered activity were calculated for liver, marrow, lungs, and bone in all groups for humans. It is worth mentioning that the radiation doses to the marrow were contributed by non-penetrating emissions in the marrow blood. The absorbed doses to the stomach and muscle were less than 9 mGy. The results in the present study represent a situation in which the extrapolation between animal data based on conventional methods may some over- or underestimate [16] the acceptable doses based on human data, and they were somewhat different from those obtained from the studies of rodents [32] as well as non-human primates. [33] This division may be particularly important if the absorbed dose estimations for humans are derived from animal models. In light of the results in this study, attention should be paid especially in situations where extrapolation between various animal species is more rational than extrapolation between animals and humans, [16] but other authors have demonstrated the usefulness of animal distribution as a model for absorbed dose estimations in humans. [34],[35],[36] Radiolabeled antibody is significantly accumulated in blood after 2 h. As observed, retention of radiopharmaceutical in the blood was significantly higher in our system, and finally at 72 h post-injection it gradually decreased. At the first 24 h post-injection, the radioactivity accumulates in the lungs due to the presence of EGFR receptors. A major problem about the described method is in selecting the time points, consistent with the mean biological half-life of antibody in humans and in rats. [15],[37] It was anticipated that all the injected activity should be cleared from the main organs in up to 41 h, and therefore time points of 2, 24, 48, 72, and 96 h were selected. Comparison between absorbed doses of different age groups is shown in [Figure 2] and it demonstrates that radiation-absorbed dose is different due to the biological differences and masses. The amount of absorbed dose for newborn and lower ages in most of the organs is significantly higher, and also this disparity in bone is as a result of skeletal system abortion in newborn, 1 year, and 5 years, at 10 years the amount of absorbed dose are equal with 15 years and adult. The newborn and children are more sensitive to radiation, so administration of radiopharmaceuticals is impermissible for them. Also, comparison between both genders demonstrates that 90 Y-DOTA-Cetuximab is a sex-dependent radiopharmaceutical, due to the difference between the amount of absorbed dose, especially in liver, bone, and kidney. The difference between the absorbed doses in some organs is caused by different hormones secreted in both genders. Considering that 90 Y-DOTA-Cetuximab is a therapeutic radiopharmaceutical which emitted just β-particles and performing dosimetry according to the MIRD method is a way for predicting therapeutic dose in radioimmunotherapy (RIT).

   Conclusion Top

Although mature, the field of radiopharmaceutical dosimetry is by no means senescent. Continued development of therapeutic applications, including use of radiolabeled monoclonal antibodies, presents significant challenges to the dosimetrist, as the traditional models of activity-that is, activity uniformly distributed in source organs, which irradiate target organs uniformly-no longer apply. In addition, the development of radiolabeled molecular probes of biologic function will also necessitate further developments in dosimetry to ensure their safe use in research.

Radiation dosimetry for 90 Y-DOTA-Cetuximab was estimated for humans based on the distribution data of 90 Y-DOTA-Cetuximab in normal rats. Previous studies have demonstrated the usefulness of animal distribution as a model for absorbed dose estimations in humans. The distribution of 90 Y-DOTA-Cetuximab in rats demonstrated high lung uptake and low muscle and spleen uptake. Although further dosimetry work should be performed on humans as 90 Y-DOTA-Cetuximab becomes useful in the clinic, these estimates can be used to predict potential absorbed doses in humans and for planning human studies.

The MIRD schema has provided an effective, uniform approach to the traditional issues of radiopharmaceutical dosimetry, and it will continue to form the foundation for enhanced dosimetry applications.

   References Top

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  [Figure 1], [Figure 2], [Figure 3]

  [Table 1], [Table 2], [Table 3], [Table 4], [Table 5]

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