Radiation Dosimetry Definition

Radiation dosimetry is the method of converting the amount of ionizing radiation deposited in tissue into its effect in tissue, which is influenced by the « damage potential » of the type of radiation (e.g., energy, size, load, half-life, etc.), the dose administered, and the dose rate [69–71]. The amounts obtained from dosimetric calculations are fundamental for radiation protection estimation, risk assessment, diagnostic dose estimation and treatment planning [72]. Dosimetry in 5 healthy human volunteers, taken at Stanford University. Dosimetry values were based on the average percentage of activity injected (% AI) into the kidneys, stomach, small intestine, bladder, pancreas, liver, lungs, heart, muscles and rest of the whole body. The mean area under the curve (AUC) of %IA was determined by analyzing the return on investment of 18F-FP-R0 1-MG-F2 static PET scans acquired immediately after tracer injection, 1 hour and 2 hours after injection. These values were entered into OLINDA to determine the radiation dosimetry for each of the organs listed in the table. The kidneys were determined to be the dose-limiting organ at 0.0490 mSV/MBq in an adult male. (Manuscript entitled « A First-in-Human Study of Integrin avb6 Cystine Knot Positron Emission Tomography (PET) Tracers » submitted for review by Kimura, R, Wang, L, Shen, B, Huo, L, Tummers, W, Filipp, F, Abou-Elkacem, L, Baratto, L, Habte, F, Devulapally, R, Witney, T, Cheng, Y, Haywood, T, Tikole, S, Chakraborti, S, Nix, J, Bonagura, C, Hatami, N, Visser, B, Poultsides, G, Norton, J, Natarajan, A, Ilovich, O, Srinivas, S, Srinivasan, A, Paulmurugan, R, Willmann, J, Chin, F, Cheng, Z, Iagaru, A, Li, F, Gambhir, S) ». Dosimetry can be a problem in some cases if the children were irradiated and the organ of interest was close to the primary radiation field. An example of environmental dosimetry is radon monitoring. Radon is a radioactive gas produced by the decay of uranium, which is present in varying amounts in the Earth`s crust. It is important to note that radon is a noble gas, while all of its decay products are metals.

The main mechanism of entry of radon into the atmosphere is diffusion through the soil. Some geographic areas, due to the underlying geology, continually produce radon that enters its path to the Earth`s surface. In some cases, the dose can be significant in buildings where gas can accumulate. Sites with higher radon noise are well mapped in each country. Outdoors, it ranges from 1 to 100 Bq/m3, let alone (0.1 Bq/m3) above the ocean. In caves or ventilated mines or poorly ventilated houses, its concentration increases to 20-2,000 Bq / m3. In the outdoor atmosphere, there is also some advection due to wind and changes in atmospheric pressure. A number of specialized dosimetry techniques are used to assess the dose that building occupants can receive.

National standards laboratories such as the National Physical Laboratory, UK (NPL) provide calibration factors for ionization chambers and other measuring instruments that are converted from the device display to absorbed dose. Standards laboratories function as a primary standard, usually calibrated by absolute calorimetry (the heating of substances as they absorb energy). A user sends their secondary standard to the lab, where they are exposed to a known amount of radiation (derived from the primary standard) and a factor is produced to convert the device`s reading into that dose. The user can then use their secondary standard to calculate the calibration factors of other devices they use, which then become tertiary standards or field instruments. Dosimetry is the process by which the amount of radioactivity administered is related to the absorbed dose of radiation in tumours, organs or the whole body. Dosimetry is important for correlating doses with clinical outcomes and, in some cases, for treatment planning to avoid excessive toxicity. In general, calculated doses for TaRT are less accurate than for external beam radiation therapy for a variety of reasons. These include limited radiation dose input data (p. e.g. few sampling points for treatment with continuous exponentially decaying irradiation), inhomogeneous dose distributions, and the assumption/calculation method used to estimate absorbed doses of TaRT.591 Dose calculation is also more complicated for internally distributed radionuclides than for external irradiation.

Alpha particle dosimetry adds complication of decay patterns and progeny, which may have a different distribution than the parent radionuclide.77,592,593 In addition, the higher biological relative efficacy (RBE) provided by treatment with alpha radionuclides compared to beta radionuclide must be considered.594 The data required to calculate the TaRT dose estimate include tumour and organ mass normal, the cumulative radioactivity absorbed by organs and tumours, and the pharmacokinetics of the radioactivity administered.595 Data are generally acquired by serial gamma camera imaging. Bone marrow dose estimates are based on imaging of bone regions of active bone marrow, such as spinal or blood pharmacokinetics.596-598 The data required to calculate the TaRT dose estimate include the mass of normal tumours and organs, the cumulative radioactivity absorbed by organs and tumours, and the pharmacokinetics of the radioactivity administered.558 Data are typically collected by captured gamma camera imaging series. Bone marrow dose estimates are based on imaging of bone regions of active bone marrow, such as spinal and/or blood pharmacokinetics.559,560 Although there have been attempts at dosimetry based on Bremsstrahlung images of radionuclides without gamma emissions, this is not commonly done. The images are of suboptimal quality, which makes it difficult to quantify precisely. Instead, estimates for non-gamma emitters are made from tracing studies using a gamma emitter that has a similar chemical composition to the therapeutic radionuclide. You can clear the dose rate alarm by retreating to a lower radiation field, but you cannot clear the dose alert until you reach an EPD drive. EPDs can also beep for every 1 or 10 μSv they record. This gives you an acoustic indication of radiation fields.

Some EPDs have wireless communication capabilities. EPDs are capable of measuring with high accuracy a wide range of radiation doses, from routine values (μSv) to emergency values (hundreds of mSv or sievert units) and can display the exposure rate as well as cumulative exposure values. Among dosimeter technologies, personal electronic dosimeters are generally the most expensive, largest, and versatile. Internal radiation dose limits The radiation dose from inhalation or ingestion of radioactive substances must also be considered in the USDA radiation protection program. The Nuclear Regulatory Commission limits the amount of radioactive material that a radiation worker can ingest into his or her body during a work year. This is called the annual intake limit (AID). These values have been calculated for several radioisotopes and are included in the tables in Appendix B of 10 CFR 20, Table 1 of the ALI occupational dose values. Weighting factors are calculated by the International Commission on Radiological Protection (ICRP) based on the risk of cancer induction for each organ and adjusted for case fatality, quality of life and associated years of life lost.