19 May 2026
11. DOSIMETRY
Gallium-68 decays with a half-life of 68 min to stable zinc-68, 89% through positron emission with a mean energy of 836 keV followed by photonic annihilation radiations of 511 keV (178%), 10% through orbital electron capture (X-ray or Auger emissions), and 3% through 13 gamma transitions from 5 excited levels.
The dosimetry of gallium (68Ga) edotreotide was calculated by Sandstrom et al. (2013), using OLINDA/EXM 1.1 software (Table 1).
Table 1 Dosimetry of gallium (68Ga) edotreotide
| Absorbed dose in selected organs | mGy/MBq |
| Organs | Mean |
| Adrenals | 0.077 |
| Brain | 0.010 |
| Breasts | 0.010 |
| Gallbladder wall | 0.015 |
| Lower large intestine wall | 0.015 |
| Small intestine | 0.023 |
| Stomach wall | 0.013 |
| Upper large intestine wall | 0.020 |
| Heart wall | 0.020 |
| Kidneys | 0.082 |
| Liver | 0.041 |
| Lungs | 0.007 |
| Muscle | 0.012 |
| Ovaries | 0.015 |
| Pancreas | 0.015 |
| Red marrow | 0.016 |
| Osteogenic cells | 0.021 |
| Skin | 0.010 |
| Spleen | 0.108 |
| Testes | 0.011 |
| Thymus | 0.011 |
| Thyroid | 0.011 |
| Urinary bladder wall | 0.119 |
| Uterus | 0.015 |
| Total body | 0.014 |
| Effective dose mSv/MBq | 0.021 |
The effective dose resulting from the administration of an activity of 200 MBq to an adult weighing 70 kg is about 4.2 mSv.
For an administered activity of 200 MBq the typical radiation absorbed dose to the critical organs, which are the urinary bladder wall, the spleen, the kidneys and the adrenals, is about 24, 22, 16 and 15 mGy, respectively.
12. INSTRUCTIONS FOR PREPARATION OF RADIOPHARMACEUTICALS
Radiation safety – Medicinal product handling
Use waterproof gloves, effective radiation shielding, and appropriate safety measures when handling the radiolabelled SomaKit TOC to avoid unnecessary radiation exposure to the patient, occupational workers, clinical personnel, and other persons.
Radiopharmaceuticals should be used by or under the control of healthcare professionals who are qualified by specific training and experienced in the safe use and handling of radionuclides, and whose experience and training have been approved by the appropriate governmental agency authorised to license the use of radionuclides.
The gallium (68Ga) edotreotide solution must be prepared in accordance with radioprotection and pharmaceutical quality standards, especially concerning aseptic technique. If at any time in the preparation of this medicinal product the integrity of the vials is compromised, the medicinal product should not be used.
A low dead space 1 ml plastic syringe must be used in order to precisely measure the adequate volume of reaction buffer to be added during the preparation. Glass syringes must not be used.
For administration, the solution should be withdrawn via the stopper using a single-dose syringe fitted with suitable protective shielding and a disposable sterile needle or using an authorised automated application system.
Method of preparation
SomaKit TOC is supplied as a kit containing two vials. It is intended to be reconstituted and radiolabelled with a gallium (68Ga) chloride solution from a generator authorised as a medicinal product and with an eluted activity up to 1 295 MBq (35 mCi).
The following authorised generators have shown to be compatible with SomaKit TOC:
• GalliaPharm, germanium-68/gallium-68 (68Ge/68Ga) radionuclide generator (Eckert & Ziegler Radiopharma GmbH),
• Galli Ad, germanium-68/gallium-68 (68Ge/68Ga) radionuclide generator (IRE-ELiT).
Refer to the Summary of Product Characteristics of the particular generator for more information.
The gallium (68Ga) edotreotide solution for intravenous injection must be prepared according to aseptic procedure, local regulation and the following instructions.
Reconstitution and radiolabelling with GalliaPharm generator:
a. If possible, for more convenience in the preparation of radiolabelled SomaKit TOC, the heating platform should be placed right beside the generator.
b. Set the temperature of the shielded dry bath with holes of 25 mm diameter at 95°C. Using a thermometer, ensure the temperature reaches the set point and stabilises before starting the reconstitution procedure.
c. Flip off the cap from the vial of powder (vial 1) and swab the top of the vial closure with an appropriate antiseptic to disinfect the surface, then allow the stopper to dry.
d. Pierce vial 1 (powder for solution for injection) septum with a 0.2 µm sterile vent filter in order to maintain atmospheric pressure within the vial during the radiolabelling process. The 0.2 µm sterile vent filter needle should not come into contact with the eluate at any time to avoid metal contamination.
e. Flip off the cap from vial 2 (reaction buffer) and swab the top of the vial closure with an appropriate antiseptic to disinfect the surface, then allow the stopper to dry. With a low dead space 1 ml sterile syringe carefully withdraw 0.5 ml reaction buffer, and keep the reaction buffer in the syringe for step “i”.
f. Connect the male luer of the outlet line of the 68Ge/68Ga generator with a sterile needle (coated with silicone or other appropriate material able to reduce metal impurity trace).
g. Connect vial 1 to the outlet line of the generator by pushing the elution needle through the rubber septum. Keep the elution needle below the 0.2 µm sterile vent filter needle. Ensure that the needles do not come into contact with each other and do not submerge in the eluate at any time.
h. Elute the generator directly into vial 1 (through the needle) according to the generator manufacturer instructions for use, in order to reconstitute the powder with an eluted activity up to 1 295 MBq (35 mCi). The elution can be performed either manually or by means of a pump.
i. At the end of the elution, disconnect the generator from vial 1, withdrawing the needle from the rubber septum, and immediately add the reaction buffer previously dosed in the 1 ml sterile syringe. Withdraw the syringe and the 0.2 µm sterile vent filter and move the vial to the hole of the dry bath at 95°C, using pliers. Leave the vial at 95°C for at least 7 minutes (do not exceed 10 minutes heating) without agitation or stirring.
j. After 7 minutes, remove the vial from the dry bath, place it in an appropriately labelled lead shield and let it cool down at room temperature for approximately 10 minutes.
k. Assay the vial radioactivity using a suitable radioactivity calibration system and record the result. Report the activity value, the calibration time, the batch number and the expiry time on the shield label included in the pack to be applied on the lead shielding container after radiolabelling.
l. Perform the quality control according to the recommended methods in order to check compliance with the specifications (see section “Quality control”).
m. The solution should be visually inspected prior to use. Only clear solutions, free from visible particles should be used. The visual inspection should be performed under a shielded screen for radioprotection purposes.
n. Store the vial containing the gallium (68Ga) edotreotide solution below 25°C until use. At the time of administration, the medicinal product must be aseptically withdrawn and the radioprotection standards must be followed. The patient dose should be measured using a suitable radioactivity calibration system immediately prior to patient administration. Medicinal product administration data should also be recorded.
A schematic representation of the radiolabelling procedure is shown in Figure 1.
Figure 1 Radiolabelling procedure when using GalliaPharm generator
Reconstitution and radiolabelling with Galli Ad generator:
a. If possible, for more convenience in the preparation of radiolabelled SomaKit TOC, the heating platform should be placed right beside the generator.
b. Set the temperature of the shielded dry bath with holes of 25 mm diameter at 95°C. Using a thermometer, ensure the temperature reaches the set point and stabilises before starting the reconstitution procedure.
c. Flip off the cap from the vial of powder (vial 1) and swab the top of the vial closure with an appropriate antiseptic to disinfect the surface, then allow the stopper to dry.
d. Pierce vial 1(powder for solution for injection) septum with a 0.2 µm sterile vent filter in order to maintain atmospheric pressure within the vial during the radiolabelling process. The 0.2 µm sterile vent filter needle should not come into contact with the eluate at any time to avoid metal contamination.
e. Flip off the cap from vial 2 (reaction buffer) and swab the top of the vial closure with an appropriate antiseptic to disinfect the surface, then allow the stopper to dry. With a low dead space 1 ml sterile syringe carefully withdraw 100 µl and keep the reaction buffer in the syringe for step “g”.
f. With a 5 ml sterile syringe and a sterile needle (coated with silicone or other appropriate material able to reduce metal impurity trace), carefully withdraw 4 ml of water for injections and reconstitute the powder in vial 1.
g. Add the reaction buffer previously dosed in the 1 ml sterile syringe.
h. Connect the male luer of the outlet line of the 68Ge/68Ga generator with a sterile needle (coated with silicone or other appropriate material able to reduce metal impurity trace).
i. Connect vial 1 to the outlet line of the generator by pushing the elution needle through the rubber septum. Keep the elution needle below the 0.2 µm sterile vent filter needle. Ensure that the needles do not come into contact with each other and do not submerge in the eluate at any time. Turn the button by 90° to the loading position, then wait 10 seconds before turning the button back to the initial position, according to the generator's instructions for use.
j. Connect vial 1 through the 0.2 µm sterile vent filter to a vacuum vial or to a pump to start the elution. Elute the generator directly into vial 1 (through the needle), with an eluted activity of up to 1 295 MBq (35 mCi).
k. At the end of the elution, first withdraw the needle from the vacuum vial in order to establish atmospheric pressure into vial 1, then disconnect vial 1 from the generator by removing the needle from the rubber septum. Finally, remove the 0.2 µm sterile vent filter and move the vial to the hole of the dry bath at 95°C, using pliers. Leave the vial at 95°C for at least 7 minutes (do not exceed 10 minutes heating) without agitation or stirring.
l. After 7 minutes, remove the vial from the dry bath, place it in an appropriately labelled lead shield and let it cool down at room temperature for approximately 10 minutes.
m. Assay the vial radioactivity using a suitable radioactivity calibration system and record the result. Report the activity value, the calibration time, the batch number and the expiry time on the shield label included in the pack to be applied on the lead shielding container after radiolabelling.
n. Perform the quality control according to the recommended methods in order to check compliance with the specifications (see section “Quality control”).
o. The solution should be visually inspected prior to use. Only clear solutions, free from visible particles should be used. The visual inspection should be performed under a shielded screen for radioprotection purposes.
p. Store the vial containing the gallium (68Ga) edotreotide solution below 25°C until use. At the time of administration, the medicinal product must be aseptically withdrawn and the radioprotection standards must be followed. The patient dose should be measured using a suitable radioactivity calibration system immediately prior to patient administration. Medicinal product administration data should also be recorded.
A schematic representation of the radiolabelling procedure is shown in Figure 2.
Figure 2 Radiolabelling procedure when using Galli Ad generator
Gallium (68Ga) edotreotide solution is stable up to 4 hours after preparation. Therefore, the radiolabelled solution can be used within 4 hours after preparation according to the radioactivity required for the administration.
Radioactive waste must be disposed of in accordance with relevant national regulations.
After radiolabelling with the correct volume of reaction buffer and generator eluate, any further dilution with any diluent is prohibited.
Quality control
Table 2 Specifications of the gallium (68Ga) edotreotide
| Test | Acceptance Criteria | Method |
| Appearance | Clear solutions free of visible particles | Visual inspection |
| pH | 3.2 – 3.8 | pH-indicator strips |
| Labelling efficiency colloidal gallium-68 species | ≤3% | Thin layer chromatography (ITLC1, see details below) |
| Labelling efficiency % Free gallium-68 | ≤2% | Thin layer chromatography (ITLC2, see details below) |
The quality controls should be performed under a shielded screen for radioprotection purposes.
Recommended method for determining labelling efficiency of gallium (68Ga) edotreotide:
ITLC1:
Material
• Glass-fibre ITLC paper (e.g. Agilent ITLC SGI001) pre-cut to 1 cm x 12 cm strips
• Mobile phase: ammonium acetate 1M: Methanol (1:1 V/V)
• Developing tank
• Radiometric TLC scanner
Sample analysis
a. The TLC developing tank is prepared by pouring the mobile phase to a depth of 3 to 4 mm. Cover the tank and allow to equilibrate.
b. Apply a drop of the gallium (68Ga) edotreotide on a pencil line 1 cm from the bottom of the ITLC strip.
c. Place the ITLC strip in the developing tank and allow it to develop for a distance of 9 cm from the point of application.
d. Scan the ITLC with a radiometric TLC scanner
e. The retention factor (Rf) specifications are as follows:
Non-complexed gallium (68Ga) = 0 to 0.1
Gallium (68Ga) edotreotide = 0.8 to 1
The labelling efficiency is calculated by integration of peak with Rf = 0 to 0.1 that must be ≤3%.
ITLC2:
Material
• Glass-fibre ITLC paper (e.g. Agilent ITLC SGI001) pre-cut to 1 cm x 12 cm strips
• Mobile phase: sodium citrate 0.1 M (pH 5) in water
• Developing tank
• Radiometric TLC scanner
Sample analysis
a. The TLC developing tank is prepared by pouring the mobile phase to a depth of 3 to 4 mm. Cover the tank and allow to equilibrate.
b. Apply a drop of the gallium (68Ga) edotreotide solution on a pencil line 1 cm from the bottom of the ITLC strip.
c. Place the ITLC strip in the developing tank and allow it to develop for a distance of 9 cm from the point of application.
d. Scan the ITLC with a radiometric TLC scanner
The retention factor (Rf) specifications are as follows:
Gallium (68Ga) edotreotide = 0.1 to 0.2
Free gallium-68 = 0.9 to 1
The labelling efficiency is calculated by integration of peak with Rf = 0.9 to 1.0 that must be ≤2%.
LEGAL CATEGORY
POM