Monday, January 26, 2015

Radiation detectors for medical applications

Radiation detectors are the Instruments that can identify the presence of radiation (in the environment, on the surface of people, inside people, and Received by people as exposure).
We use radiation detectors to know where radiation energy came from and how many / how much it is.

 There are two basic types of instruments used for radiation detection:
1.   Particle counting instruments (Gas Filled Detectors, Solid and Liquid Scintillation Detectors).
2.   Dose measuring instruments (Pocket dosimeters, film badges, and personal thermo luminescent dosimeters).

The particle counting instruments are measuring the number of particles (electrons, alphas, protons, neutrons, etc.) or photons that give a signal in the detector, and give the result in counts per minute (cpm) or counts per second (cps).

The dose measuring instruments are also measuring the number of particles or photons, but the result is given in units of dose (R, Gy, Sv, etc.), or dose rate (R/s, mSv/h, Gy/min, etc.).

 Some types of commonly used detectors:

Geiger counter: The detector most common to the public is the Geiger-Mueller counter, commonly called the Geiger counter. It uses a gas-filled tube with a central wire at high voltage to collect the ionization produced by incident radiation. It can detect alpha, beta, and gamma radiation although it cannot distinguish between them. Because of this and other limitations, it is best used for demonstrations or for radiation environments where only a rough estimate of the amount of radioactivity is needed.
Geiger counter in use (Photo credit: Wikipedia)
Scintillation detectors: Scintillators are usually solids (although liquids or gases can be used) that give off light when radiation interacts with them. The light is converted to electrical pulses that are processed by electronics and computers. Examples are sodium iodide (NaI) and bismuth germanate (BGO). These materials are used for radiation monitoring, in research, and in medical imaging equipment.

Solid state X-ray and gamma-ray detectors: Silicon and germanium detectors, cooled to temperatures slightly above that of liquid nitrogen (77 K), are used for precise measurements of X-ray and gamma-ray energies and intensities. Silicon detectors are good for X-rays up to about 20 keV in energy. Germanium detectors can be used to measure energy over the range of >10 keV to a few MeV. Such detectors have applications in environmental radiation and trace element measurements. Germanium gamma ray detectors play the central role in nuclear high-spin physics, where gamma rays are used to measure the rotation of nuclei

Personal Thermo luminescent dosimeter (TLD): A small radiation monitoring device worn by persons entering environments that may contain radiation. It uses lithium fluoride crystals to record radiation exposure, not sensitive to heat and humidity and Available for use on torso and finger.

Measuring radiation inside people:

  The main paths for internal irradiation of those working with radioactive materials are inhalation and ingestion.

There are two internal dosimetry programs have been developed for measuring internal irradiation of personnel:

1.   Iodine measurement: I-131 is gamma emitters. Therefore, a gamma detector can be used to measure the iodine content of the person's thyroid. Proper calibration of the instrument is done using 'phantoms' that mimic human body composition. After gathering information about thyroid activity (in Bq) and the moment of iodine usage, we can estimate iodine uptake and intake. Since the level of radioiodine in the thyroid decreases after 5 days, the measurement must be done between 1 and 4 days after usage. The amount of radioiodine in the thyroid is compared with the annual limit on intake (ALI) and the dose received by the contaminated person can be estimated.  

2.   Urinalysis: most of the radionuclides tend to be eliminated in body fluids. By measuring activity content in urine, we can estimate the uptake and the intake. The dose is estimated by comparing the intake with the (ALI) for that particular radionuclide.