Currently, the standard 18-column periodic table contains 118 elements. Nuclides of elements that are capable of spontaneous radioactive transformation of nuclei are called radionuclides. During this radioactive transformation, radioactive radiation is released. There are many more radionuclides than stable nuclides, currently around 2000 are known. Each element is represented by several radioisotopes. Some radionuclides, especially those with a high nuclear number, can undergo further transformation after decay (decay series) and thereby increase the radiation load of the organism. Each radionuclide has its characteristic half-life, type of transformation and activity.
Radionuclides are used in medicine for labeling various substances, monitoring their amount and metabolism.
- quantitative methods monitor the amount of radiation from the sample,
- qualitative methods are used to determine the distribution of the radionuclide (in organs, cells).
A summary of individual radionuclides used in nuclear medicine and their characteristic properties is shown in the chart:
The Chart of Radionuclides Used in Nuclear Medicine[edit | edit source]
|radionuklides||half-time||a kind of transformation||energy|
|11C||20 minutes||beta+, positrons||0.96 MeV|
|13N||10 minutes||beta+,positrons||1.19 MeV|
|15O||2 minutes||beta+,positrons||1.73 MeV|
|18F||110 minutes||beta+,positrons||0.635 MeV|
|68Ga||68 minutes||beta+,positrons||1.9 MeV|
|82Rb||1.3 minutes||beta+,positrons||3.15 MeV|
|57Co||272 days||EZ, gamma||122 keV|
|51Cr||27,7 days||EZ, gamma||320 keV|
|67Ga||78 hours||EZ, gamma||91, 185, 300, 394 keV|
|123I||13 hours||EZ, gamma||157 KeV|
|125I||60 days||EZ, gamma||35 keV|
|131I||8 days||beta-,beta; gamma||606 keV; 80, 284 364 keV|
|111In||2,8 days||EZ, gamma||171, 245 keV|
|81mKr||13,3 seconds||IP, gamma||190 keV|
|99Mo||67 hours||beta-,beta; gamma||1.214 MeV; 141,181,740 keV|
|32P||14,3 days||beta-,beta||1.709 MeV|
|153Sm||47 hours||beta-,beta; gamma||630, 700, 803 keV; 103 keV (34%)|
|89Sr||50,5 days||beta-,beta||1.488 MeV|
|99mTc||6 hours||IP, gamma||140 keV|
|201Tl||73 hours||EZ, gamma||78, 167 keV|
|133Xe||36,4 days||EZ, gamma||172, 203 keV|
|90Y||64 hours||beta-,beta||2,28 MeV|
|186Re||90,6 hours||beta-,beta; gamma||1.07 MeV; 137 keV|
|223Ra||11,4 days||alpha||5.75 MeV|
|211At||7,2 hours||alpha||5.87 MeV|
|212Bi||1,01 hours||alpha + beta-, alpha; beta||6.09 MeV; 2.25 MeV|
Use of Radionuclides[edit | edit source]
Laboratory methods based on radiation detection (e.g. RIA) are giving way to new methods (ELISA) that do not use ionizing radiation, as work with radionuclides requires expensive security and means higher risk. Previously, however, they were the only way to monitor cellular events (DNA synthesis, metabolic pathways, etc.).
Radioisotopes play an absolutely key role in nuclear medicine, where they are used to produce radiopharmaceuticals. We distinguish between radionuclides for diagnostic and therapeutic use. Their distribution is then monitored by special devices (e.g. PET, Gamma-camera, ...).
Diagnostic Radionuclides[edit | edit source]
99mTechnetium[edit | edit source]
99mTechnetium (zkráceně 99mTc) is today the most commonly used radioisotope in scintillation examinations in nuclear medicine. The letter m denotes the metastable state of the nucleus, which is at a higher energy level and emits γ photons during deexcitation.
Compared to other radionuclides, it has many advantages. It is easily obtained by the decay of artificially prepared 99molybdenum, which is most often placed in a radionuclide generator. The energy of its photons is 140 keV and the half-life is about 6 hours, meaning a small radiation load for the organism. At the same time, its energy is sufficient for good radiation detection. A short half-life allows the administration of a radiopharmaceutical with higher activity, which gives us better examination results (more signals).
99mTc is obtained from generators in the form of pertechnate (technetate) TcO-4. This can be directly used in the examination of the thyroid gland. The reduction of pertechnate with stannous chloride produces a substance that very willingly participates in other chemical reactions, which is used to attach to a carrier (identification of the substance).
67Gallium[edit | edit source]
67Ga is administered in the form of 67Ga-citrate when examining tumors and inflammation. It is specifically taken up in the hepatocellular ca., lymphomas, malignant melanoma and in soft tissue sarcomas. It is also used to locate inflammatory foci. But it can also accumulate physiologically in the active tissue of the thymus and thyroid gland.
Iodine Radionuclides[edit | edit source]
Unbound 131I is the longest-used radionuclide. It is a mixed β and γ emitter. The β component causes tissue radiation and is not scintigraphically detectable, therefore 131 I is not recommended for diagnostic examinations. It is widely used in the therapy of differentiated carcinomas of the thyroid gland (not medullary!). Doses with less activity are given in hyperactive goiter. The γ component of radiation is suitable for monitoring the course of therapy (post-therapeutic scintigraphy), or for diagnostic purposes to search for metastases. In the diagnosis of thyroid cancers we administer a smaller dose than during therapy.
In the case of nuclear accidents, it is necessary to give the population non-radioactive iodine, which saturates the thyroid gland. Otherwise, radioactive iodine would be trapped and, when it decays, it could lead to malignancies and severe damage to the gland.
Unbound 123I and 125I can be used for purely diagnostic purposes, they are picked up similarly to 131 I. In bound form, they are used like other radionuclides, e.g. in the labeling of monoclonal antibodies (125 I-MoAb).
18Fluorine[edit | edit source]
18F is a positron emitter. In the form of 18F-FDG (fluorodeoxyglucose), it is the most widely used radiopharmaceutical in PET examinations, when glucose metabolismin the examined area is displayed. Its disadvantages are a short half-life, the supply of fluorine must therefore be very fast (accelerators must be close by), high energy of annihilation radiation (2x 511 keV) and high requirements for radiation protection.
201Thallium[edit | edit source]
201Tl is an artificial radionuclide which, with T1/2=72 hours ransforms into the mercury isotope 201Hg. 201Tl is used in myocardial perfusion scintigraphy. One of the disadvantages of 201Tl Tl is its long half-life, which creates a greater burden on the body. That is why today it is replaced by the isotope Technetium 99mTc, which has a similar use, but thanks to its T1/2=6 hours it burdens the body less.
111Indium[edit | edit source]
111In is used in immunoscintigraphy to diagnose cancer.
81mKr - Krypton[edit | edit source]
Is used in scintigraphy of pulmonary ventilation.
Other Radionuclides[edit | edit source]
Other radionuclides used include:
- 11C, 13C – short half-life, used in lung ventilation scintigraphy and in the breath test with labeled urea;
- 45Ca – examination of bone metabolism;
- 32P – monitoring of metabolic events in cells (e.g. DNA synthesis).
Therapeutic Radionuclides[edit | edit source]
As therapeutic radionuclides, we use those that have high activity and a short radiation range. Radionuclides, which are specifically absorbed in tissues and undergo β transformation , are used in the therapy of certain cancer diseases. Open α emitters are not yet used therapeutically. However, research is currently underway that could change this fact. α emitters have a very short range, with a specific application they would only destroy tumor tissues. But their radiation is so "hard" (high LET → tissue damage) that we would rather burden the patient.
131I - Iodine[edit | edit source]
90Y - Yttrium[edit | edit source]
It is administered in the form of a colloid and is used for radionuclide synovectomy.
89Sr - Strontium[edit | edit source]
Production of Radionuclides[edit | edit source]
Nowadays, only artificially prepared radionuclides that achieve high purity are used for the needs of nuclear medicine. They are obtained from:
Production in a Cyclotron[edit | edit source]
Positively charged particles (deuterons, protons, helium nuclei) are accelerated and hit a target made of "mother" elements. Through nuclear interactions, they are built into the structure of the target atoms and change their nuclear and proton numbers → change of elements. After irradiation, a radionuclide is released from the target by chemical reactions, the remaining "parent" element does not react and is not released.
- Radionuclides Produced in Cyclotrons
- other radionuclides can also be produced (e.g. 67Ga), but generators are more suitable for obtaining them (see below).
Nuclear Reactors[edit | edit source]
Radioisotopes can be obtained from nuclear reactors that most often fission 235U by isolating them from the fission products, and the resulting neutrons can be used.
Neutrons , produced by the fission of uranium, are too fast, have high energy, and when they interact with the nucleus, it would split. Therefore, it is necessary to slow down (moderate) neutrons. Slow, so-called thermal, neutrons then easily combine with the nucleus, often with the emission of a γ photon.
Similar radionuclides are obtained from fission products as from neutron interactions. Different chemical methods are used for purification (distillation, chromatography, precipitation). However, only radionuclides with a longer half-life can be obtained.
- Radionuclides obtained from reactors or by neutron irradiation
Radionuclide generators[edit | edit source]
Due to their price, size, simplicity and ease of use, they are the most widely used source of radionuclides.
- Generator 99Mo → 99mTc
- Generator 81Rb → 81mKr
- Generator 68Ge → 68Ga
- Generator 90Sr → 90Y
Generator 99Mo -> 99mTc[edit | edit source]
99Mo (T ½ 66 h.) → 99mTc (T ½ 6 h.) → 99Tc (2.1x105 years) The basis is a lead-shielded column containing aluminum oxide with adsorbed 99Mo (T ½ 66 hodin). 99Mo is converted by beta-decay to99mTc, which is very weakly bound to aluminum oxide and is washed out by elution with sterile physiological solution into a sterile lead-shielded vacuum vial. The generator is usable for two weeks.
Generator 81Rb -> 81mKr[edit | edit source]
81Rb (T ½ 4.6 h.) → 81mKr (T ½ 13 s., 191 keV) he generator is placed in a lead cover directly next to the patient and gaseous 81mKr is washed out by the air stream. The distribution of radioactivity in the lungs after inhalation is visualized by a gamma camera.
Generator 68Ge -> 68Ga[edit | edit source]
Generator 90Sr -> 90Y[edit | edit source]
90Sr (T ½ 28 let) → 90Y (T ½ 64.2 hodin) 90Y – used for radiation synovectomy.
Links[edit | edit source]
Related Articles[edit | edit source]
Source[edit | edit source]
- ULLMANN, Vojtěch. 1.Jaderná a radiační fyzika [online]. [cit. 2014-12-05]. <http://astronuklfyzika.cz/JadRadFyzika4.htm>.
- SKALICKÁ, Zuzana – HALAŠKA, Jiří, et al. 4.3.1. Zdroje Ionizujícího záření využívané ve zdravotnictví [online]. [cit. 2014-12-05]. <http://fbmi.sirdik.org/4-kapitola/43/431.html>.
References[edit | edit source]
- KUPKA, Karel – KUBINYI, Jozef – ŠÁMAL, Martin, et al. Nukleární medicína. 1. edition. [s.n.] 2007. 185 pp. ISBN 978-80-903584-9-2.