A radiation dosimeter is a device that measures dose uptake of external ionizing radiation. It is worn by the person being monitored when used as a personal dosimeter, and is a record of the radiation dose received. Modern electronic personal dosimeters can give a continuous readout of cumulative dose and current dose rate, and can warn the wearer with an audible alarm when a specified dose rate or a cumulative dose is exceeded. Other dosimeters, such as thermoluminescent or film types, require processing after use to reveal the cumulative dose received, and cannot give a current indication of dose while being worn.
The personal ionising radiation dosimeter is of fundamental importance in the disciplines of radiation dosimetry and radiation health physics and is primarily used to estimate the radiation dose deposited in an individual wearing the device.
Ionising radiation damage to the human body is cumulative, and is related to the total dose received, for which the SI unit is the sievert. Workers exposed to radiation, such as radiographers, nuclear power plant workers, doctors using radiotherapy, those in laboratories using radionuclides, and HAZMAT teams are required to wear dosimeters so a record of occupational exposure can be made. Such devices are known as "legal dosimeters" if they have been approved for use in recording personnel dose for regulatory purposes.
Dosimeters are typically worn on the outside of clothing, a "whole body" dosimeter is worn on the chest or torso to represent dose to the whole body. This location monitors exposure of most vital organs and represents the bulk of body mass. Additional dosimeters can be worn to assess dose to extremities or in radiation fields that vary considerably depending on orientation of the body to the source.
Common types of personal dosimeters for ionizing radiation include:
Electronic personal dosimeter
The electronic personal dosimeter is an electronic device that has a number of sophisticated functions, such as continual monitoring which allows alarm warnings at preset levels and live readout of dose accumulated. These are especially useful in high dose areas where residence time of the wearer is limited due to dose constraints. The dosimeter can be reset, usually after taking a reading for record purposes, and thereby re-used multiple times.
1. The MOSFET dosimeter is direct reading with a very thin active area (less than 2 μm).
2. The physical size of the MOSFET when packaged is less than 4 mm.
3. The post radiation signal is permanently stored and is dose rate independent.
Gate oxide of MOSFET which is conventionally silicon dioxide is an active sensing material in MOSFET dosimeters. Radiation creates defects (acts like electron-hole pairs) in oxide, which in turn affects the threshold voltage of the MOSFET. This change in threshold voltage is proportional to radiation dose. Alternate high-k gate dielectrics like Hafnium dioxide and Aluminum oxides are also proposed as a radiation dosimeters.
A thermoluminescent dosimeter measures ionizing radiation exposure by measuring the intensity of visible light emitted from a crystal in the detector when heated. The intensity of light emitted is dependent upon the radiation exposure. These were once sold surplus and one format resembled a dark green wristwatch containing the active components and a highly sensitive IR diode mounted to the LiF glass chip.[clarification needed] The main advantage is that the chip records dosage passively until exposed to light or heat so even a used sample can provide valuable scientific data.
Film badge dosimeter
Film badge dosimeters are for one-time use only. The level of radiation absorption is indicated by a change to the film emulsion, which is shown when the film is developed. They are now mostly superseded by electronic personal dosimeters and thermoluminescent dosimeters.
Quartz fiber dosimeter
These use the property of a quartz fiber to measure the static electricity held on the fiber. Before use by the wearer a dosimeter is charged to a high voltage, causing the fiber to deflect due to electrostatic repulsion. As the gas in the dosimeter chamber becomes ionized by radiation the charge leaks away, causing the fiber to straighten and thereby indicate the amount of dose received against a graduated scale, which is viewed by a small in-built microscope. They are only used for short durations, such as a day or a shift, as they can suffer from charge leakage, which gives a false high reading.
They are now largely superseded by electronic personal dosimeters for short term monitoring.
Geiger tube dosimeter
These use a conventional Geiger-Muller tube typically a ZP1301 or similar energy compensated tube requiring between 600 and 700V and a low power counter IC[clarification needed] with display driver. The display on most was a bubble type with 4 digits though some newer units used a liquid crystal display module, and a button to enable the display for long battery life. The voltage was derived from a small step-up that often used a unijunction transistor which though expensive was reliable over time and especially in high radiation environments common with tunnel diodes. These have the disadvantage that the stored becquerel or microsievert count is volatile and vanishes if the power supply gets disconnected though there can be a capacitor to prevent this. The fix was to use a long life battery, knurled high quality contacts and security screws to hold the typically glass front panel in place.
Dosimetry dose quantities
The operational quantity for personal dosimetry is the personal dose equivalent, which is defined by the International Commission on Radiological Protection as the dose equivalent in soft tissue at an appropriate depth, below a specified point on the human body. The specified point is usually given by the position where the individual’s dosimeter is worn.
Instrument and dosimeter response
This is an actual reading obtained from such as an ambient dose gamma monitor, or a personal dosimeter. The dosimeter is calibrated in a known radiation field to ensure display of accurate operational quantities and allow a relationship to known health effect. The personal dose equivalent is used to assess dose uptake, and allow regulatory limits to be met. It is the figure usually entered into the records of external dose for occupational radiation workers.
The dosimeter plays an important role within the international radiation protection system developed by the International Commission on Radiological Protection and the International Commission on Radiation Units and Measurements. This is shown in the accompanying diagram.
The "slab" phantom is used to represent the human torso for calibration of whole body dosimeters. This replicates the radiation scattering and absorption effects of the human torso. The International Atomic Energy Agency states "The slab phantom is 300 mm × 300 mm × 150 mm depth to represent the human torso".
|Activity (A)||becquerel||Bq||s−1||1974||SI unit|
|curie||Ci||3.7 × 1010 s−1||1953||3.7×1010 Bq|
|rutherford||Rd||106 s−1||1946||1,000,000 Bq|
|Exposure (X)||coulomb per kilogram||C/kg||C⋅kg−1 of air||1974||SI unit|
|röntgen||R||esu / 0.001293 g of air||1928||2.58 × 10−4 C/kg|
|Absorbed dose (D)||gray||Gy||J⋅kg−1||1974||SI unit|
|erg per gram||erg/g||erg⋅g−1||1950||1.0 × 10−4 Gy|
|rad||rad||100 erg⋅g−1||1953||0.010 Gy|
|Equivalent dose (H)||sievert||Sv||J⋅kg−1 × WR||1977||SI unit|
|röntgen equivalent man||rem||100 erg⋅g−1 x WR||1971||0.010 Sv|
Process irradiation verification
Manufacturing processes that treat products with ionizing radiation, such as food irradiation, use dosimeters to calibrate doses deposited in the matter being irradiated. These usually must have a greater dose range than personal dosimeters, and doses are normally measured in the unit of absorbed dose: the gray (Gy). The dosimeter is located on or adjacent to the items being irradiated during the process as a validation of dose levels received.
Chromoradiometer or colour dosimeter by Guido Holzknecht (1902)
- Comparison of dosimeters
- Geiger counter
- Ionisation chamber
- Operational instruments of the Royal Observer Corps
- Scintillation counter
- "Archived copy" (PDF). Archived from the original (PDF) on 2015-04-10. Retrieved 2015-04-04.CS1 maint: archived copy as title (link)
- Senthil Srinivasan, V.S.; Pandya, Arun (2011). "Dosimetry aspects of hafnium oxide metal-oxide-semiconductor (MOS) capacitor". Thin Solid Films. 520 (1): 574–577. Bibcode:2011TSF...520..574S. doi:10.1016/j.tsf.2011.07.010.
- Frame, Paul (2007-07-25). "Pocket Chambers and Pocket Dosimeters". Health physics historical instrument museum collection. Oak Ridge Associated Universities. Retrieved 2008-11-08.
- International Commission on Radiological Protection pub 103 glossary.
- International Atomic Energy Agency safety report 16
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