Iodine-123

Iodine-123 is produced in a cyclotron by proton irradiation of xenon in a capsule. Xenon-124 absorbs a proton and immediately loses a neutron and proton to form xenon-123, or else loses two neutrons to form caesium-123, which decays to xenon-123. The xenon-123 formed by either route then decays to iodine-123, and is trapped on the inner wall of the irradiation capsule under refrigeration, then eluted with sodium hydroxide in a halogen disproportionation reaction, similar to collection of iodine-125 after it is formed from xenon by neutron irradiation (see article on ¹²⁵I for more details).

¹²⁴
Xe (p,pn) ¹²³
Xe → ¹²³
I

¹²⁴
Xe (p,2n) ¹²³
Cs → ¹²³
Xe → ¹²³
I

Iodine-123 is usually supplied as [¹²³
I]-sodium iodide in 0.1 M sodium hydroxide solution, at 99.8% isotopic purity.[2]

¹²³I for medical applications has also been produced at Oak Ridge National Laboratory by proton cyclotron bombardment of 80% isotopically enriched tellurium-123.[3]

¹²³
Te (p,n) ¹²³
I

The detailed decay mechanism is electron capture (EC) to form an excited state of the nearly-stable nuclide tellurium-123 (its half life is so long that it is considered stable for all practical purposes). This excited state of ¹²³Te produced is not the metastable nuclear isomer ^123mTe (the decay of ¹²³I does not involve enough energy to produce ^123mTe), but rather is a lower-energy nuclear isomer of ¹²³Te that immediately gamma decays to ground state ¹²³Te at the energies noted, or else (13% of the time) decays by internal conversion electron emission (127 keV),[4] followed by an average of 11 Auger electrons emitted at very low energies (50-500 eV). The latter decay channel also produces ground-state ¹²³Te. Especially because of the internal conversion decay channel, ¹²³I is not an absolutely pure gamma-emitter, although it is sometimes clinically assumed to be one.

The Auger electrons from the radioisotope have been found in one study to do little cellular damage, unless the radionuclide is directly incorporated chemically into cellular DNA, which is not the case for present radiopharmaceuticals which use ¹²³I as the radioactive label nuclide. The damage from the more penetrating gamma radiation and 127 keV internal conversion electron radiation from the initial decay of ¹²³Te is moderated by the relatively short half-life of the isotope.[5]

¹²³I is the most suitable isotope of iodine for the diagnostic study of thyroid diseases. The half-life of approximately 13.2 hours is ideal for the 24-hour iodine uptake test and ¹²³I has other advantages for diagnostic imaging thyroid tissue and thyroid cancer metastasis. The energy of the photon, 159 keV, is ideal for the NaI (sodium iodide) crystal detector of current gamma cameras and also for the pinhole collimators. It has much greater photon flux than ¹³¹I. It gives approximately 20 times the counting rate of ¹³¹I for the same administered dose, while the radiation burden to the thyroid is far less (1%) than that of ¹³¹I. Moreover, scanning a thyroid remnant or metastasis with ¹²³I does not cause "stunning" of the tissue (with loss of uptake), because of the low radiation burden of this isotope.[6] For the same reasons, ¹²³I is never used for thyroid cancer or Graves disease treatment, and this role is reserved for ¹³¹I.

¹²³I is supplied as sodium iodide (NaI), sometimes in basic solution in which it has been dissolved as the free element. This is administered to a patient by ingestion under capsule form, by intravenous injection, or (less commonly due to problems involved in a spill) in a drink. The iodine is taken up by the thyroid gland and a gamma camera is used to obtain functional images of the thyroid for diagnosis. Quantitative measurements of the thyroid can be performed to calculate the iodine uptake (absorption) for the diagnosis of hyperthyroidism and hypothyroidism.

Dosing can vary; 7.5–25 megabecquerels (200–680 μCi) is recommended for thyroid imaging[7][8] and for total body while an uptake test may use 3.7–11.1 MBq (100–300 μCi).[9][10] There is a study that indicates a given dose can effectively result in effects of an otherwise higher dose, due to impurities in the preparation.[11] The dose of radioiodine ¹²³I is typically tolerated by individuals who cannot tolerate contrast mediums containing larger concentration of stable iodine such as used in CT scan, intravenous pyelogram (IVP) and similar imaging diagnostic procedures. Iodine is not an allergen.[12]

Sequence of 123-iodide human scintiscans after an intravenous injection, (from left) after 30 minutes, 20 hours, and 48 hours. A high and rapid concentration of radio-iodide is evident in cerebrospinal fluid (left), gastric and oral mucosa, salivary glands, arterial walls, ovary and thymus. In the thyroid gland, I-concentration is more progressive, as in a reservoir (from 1% after 30 minutes, and after 6, 20 h, to 5.8% after 48 hours, of the total injected dose).(Venturi, 2011)

¹²³I is also used as a label in other imaging radiopharmaceuticals e.g.metaiodobenzylguanidine (MIBG) and ioflupane.

Removal of radioiodine contamination can be difficult and use of a decontaminant specially made for radioactive iodine removal is advised. Two common products designed for institutional use are Bind-It[13] and I-Bind. General purpose radioactive decontamination products are often unusable for iodine, as these may only spread or volatilize it.

• Isotopes of iodine
• Iodine-125
• Iodine-129
• Iodine-131
• Iodine in biology