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Radiation Dosimeter

A radiation dosimeter is a device that measures exposure to ionizing radiation. Dosimeters usually record a dose, the absorbed radiation energy measured in grays (Gy), or the equivalent dose measured in sieverts (Sv). A personal dosimeter is a dosimeter worn at the body’s surface by the person being monitored and records the radiation dose received.

EPD - Electronic Personal Dosimeters
EPD – Electronic Personal Dosimeters

Commercially available dosimeters range from low-cost, passive devices that store personnel dose information for later readout to more expensive, battery-operated devices that display immediate dose and dose rate information (typically an electronic personal dosimeter). Readout method, dose measurement range, size, weight, and price are important selection factors.

There are two kinds of dosimeters:

  • Passive Dosimeters. Commonly used passive dosimeters are the Thermo Luminescent Dosimeter (TLD) and the film badge. A passive dosimeter produces a radiation-induced signal stored in the device, and the dosimeter is then processed, and the output is analyzed.
  • Active Dosimeters. You can use an active dosimeter, typically an electronic personal dosimeter (EPD), to get a real-time exposure value. An active dosimeter produces a radiation-induced signal and displays a direct reading of the detected dose or dose rate in real-time.

The passive and the active dosimeters are often used together to complement each other. Dosimeters must be worn on a position of the body representative of its exposure to estimate effective doses, typically between the waist and the neck, on the front of the torso, facing the radioactive source. Dosimeters are usually worn outside clothing, around the chest or torso to represent dose to the “whole body.” Dosimeters may also be worn on the extremities or near the eye to measure equivalent doses to these tissues.

Radiation dosimeters and detectors can also be categorized according to their purpose. It must be noted that the following devices are not necessary dosimeters, and these devices are used for dosimetry in nuclear power plants:

  • Personal Dosimeters. Personal dosimetry is a key part of radiation dosimetry. Personal dosimetry is used primarily (but not exclusively) to determine doses for individuals exposed to radiation related to their work activities. These doses are usually measured by devices known as personal dosimeters.
  • Gamma Survey Meters. Portable survey meters are radiation detectors used by radiological technicians to measure ambient dose rates. These portable instruments usually have rate meters. In nuclear facilities, these portable survey meters are typically used by radiation protection technicians.
  • Contamination Meters. Contamination meters are instruments for surface contamination measurement. In nuclear facilities, contamination monitors are usually installed at the exit from the controlled areas. These monitors may utilize proportional counters with a large area, thin window detector similar to Hand & Shoe Monitors.
  • Full-Body Monitors. Full-Body Monitors, or Whole-Body Monitors, are instruments for surface contamination measurement. They are used for personnel exit monitoring, the term used in radiation protection for checking for external contamination (or surface contamination) of a whole body of a person leaving radioactive contamination controlled area.
  • Gamma Spectrometers. A gamma-ray spectrometer (GRS) is a sophisticated device for measuring the energy distribution of gamma radiation. For the measurement of gamma rays above several hundred keV, there are two detector categories of major importance, inorganic scintillators such as NaI(Tl) and semiconductor detectors.

Most personal dosimeters in use today mustn’t be absolute instruments but reference instruments, which means they must be periodically calibrated. When a reference dosimeter is calibrated, a calibration factor can be determined. This calibration factor relates the exposure quantity to the reported dose. The validity of the calibration is demonstrated by maintaining the traceability of the source used to calibrate the dosimeter. The traceability is achieved by comparison of the source with a “primary standard” at a reference calibration center. In monitoring individuals, the values of these operational quantities are taken as a sufficiently precise assessment of effective dose and skin dose, respectively, if their values are below the protection limits.

Characteristics of Dosimeters – Key Features

There are many types of dosimeters and detectors, each with limitations. Many factors influence the quality of a dosimeter’s results. Some key considerations when choosing a dosimeter include:

  • Type of radiation. Each type of radiation interacts with matter differently, and this consideration is crucial. For doses from neutrons, we cannot use a simple GM counter.
  • The energy of radiation. A dosimeter’s response will vary depending on the energy of the radiation and the angle(s) between the source and the dosimeter’s detector.
  • Fading. A dosimeter’s signal can be lost or fade over time, caused by external factors such as temperature, light, and humidity.
  • Direct reading. Sometimes, it is of the highest importance that the dosimeter can give a continuous readout of the cumulative dose and current dose rate and warn the person wearing it when a specified dose rate or a cumulative dose is exceeded.
  • Minimum measurable dose. The lowest dose can be measured with a certain specified confidence level.
  • Ruggedness and ease of wear. Dosimeters differ in their ability to withstand severe environmental conditions. Some are heavy for a given purpose, and some are smaller, lighter, and more portable.

As can be seen, radiation dosimetry is very difficult since no single dosimeter will have every one of these characteristics. Therefore, a dosimeter user must understand the environment where the instrument will be used. In most practical situations, dosimeters provide reasonable approximations to the personal dose equivalent, Hp(d), at least at the location of the dosimeter. It must be noted that the personal dose equivalent generally overestimates the effective dose. On the other hand, this procedure is valid only at low doses and under the assumption of a uniform whole-body exposure. However, this procedure might not be sufficient for high personal doses approaching or exceeding the annual dose limit or in strongly inhomogeneous radiation fields.

See also: The Radiation Dosimeters for Response and Recovery Market Survey Report. National Urban Security Technology Laboratory. SAVER-T-MSR-4. <available from: https://www.dhs.gov/sites/default/files/publications/Radiation-Dosimeters-Response-Recovery-MSR_0616-508_0.pdf>.

Types of Dosimeters

Film Badge Dosimeters

Film badges are small portable devices for monitoring cumulative radiation dose due to ionizing radiation. The principle of operation is similar to X-ray pictures. The badge consists of two parts: photographic film and a holder. The film is contained inside a badge. The piece of photographic film is sensitive material, and it must be removed monthly and developed. The more radiation exposure, the more blackening of the film. The blackening of the film is linear to the dose, and doses up to about 10 Gy can be measured.

See also: Film Badge Dosimeter

TLD – Thermoluminescent Dosimeter

A thermoluminescent dosimeter, abbreviated as TLD,  is a passive radiation dosimeter that measures ionizing radiation exposure by measuring the intensity of visible light emitted from a sensitive crystal in the detector when the crystal is heated. The intensity of light emitted is measured by the TLD reader, depending on the radiation exposure. Thermoluminescent dosimeters were invented in 1954 by Professor Farrington Daniels of the University of Wisconsin-Madison. TLD dosimeters apply to situations where real-time information is not needed. Still, precise accumulated dose monitoring records are desired for comparison to field measurements or for assessing the potential for long-term health effects.

See also: TLD – Thermoluminescent Dosimeter

EPD – Electronic Personal Dosimeter

An electronic personal dosimeter is a modern dosimeter that can give a continuous readout of cumulative dose and current dose rate and warn the person wearing it when a specified dose rate or a cumulative dose is exceeded. EPDs are especially useful in high-dose areas where the residence time of the wearer is limited due to dose constraints.

The electronic personal dosimeter, EPD, can display a direct reading of the detected dose or dose rate in real-time. Electronic dosimeters may be used as supplemental dosimeters as well as primary dosimeters. The passive and electronic personal dosimeters are often used together to complement each other.

See also: EPD – Electronic Personal Dosimeter

MOSFET Dosimeter

MOSFET dosimeter is a small portable device for monitoring and direct reading radiation dose rate. Since it is based on the MOSFET transistor, the metal-oxide-semiconductor field-effect transistor (MOSFET), the principle of operation is similar to semiconductor detectors. MOSFET dosimeters are now used as clinical dosimeters for radiotherapy radiation beams. Their main advantage is their physical size, which is less than 4 mm2. In radiation therapy dosimetry, MOSFET dosimeters often replace TLD dosimeters since they offer immediate readout.

See also: MOSFET Dosimeter

Self-reading Dosimeter

Self Indicating Pocket Dosimeters - Quartz Fiber Dosimeter
The self-indicating pocket dosimeter consists of an ionization chamber with a volume of approximately two milliliters sensitive to the desired radiation, a quartz fiber electrometer to measure the charge, and a microscope to read the fiber image off a scale. Source: www.nde-ed.org

Self-reading dosimeters are field-readable devices worn on the body to measure an accumulated dose. These are unpowered devices that do not contain a battery. Devices in this group include:

  • Quartz fiber dosimeter. A quartz fiber dosimeter, called a self-indicting pocket dosimeter (SIPD), is a pen-like device that measures the cumulative dose of ionizing radiation received by the device, usually over one work period.
  • Self-developing photochemical cards. The self-developing photochemical card is a credit card-sized, instant color-developing emergency dosimeter. It is designed to monitor exposure in a radiological incident for medical treatment triage and minimize worry and panic.

See also: Self-reading Dosimeter

DIS Dosimeter

DIS Dosimeter
DIS Dosimeter Source: https://www.mirion.com/products/dosimetry-system

Direct-ion storage dosimeter, DIS, is an electronic dosimeter from which the dose information for both Hp(10) and Hp(0.07) can be obtained instantly at the workplace using an electronic reader unit. The DIS dosimeter is based on the combination of an ion chamber and a non-volatile electronic charge storage element. DIS dosimeter uses an analog memory cell inside a small, gas-filled ionization chamber. Incident radiation causes ionizations in the chamber wall and the gas, and the charge is stored for subsequent readout. The DIS dosimeter is read at the user’s site by connecting to an electronic reader unit.


Radiation Protection:

  1. Knoll, Glenn F., Radiation Detection and Measurement 4th Edition, Wiley, 8/2010. ISBN-13: 978-0470131480.
  2. Stabin, Michael G., Radiation Protection, and Dosimetry: An Introduction to Health Physics, Springer, 10/2010. ISBN-13: 978-1441923912.
  3. Martin, James E., Physics for Radiation Protection 3rd Edition, Wiley-VCH, 4/2013. ISBN-13: 978-3527411764.
  5. U.S. Department of Energy, Instrumentation, and Control. DOE Fundamentals Handbook, Volume 2 of 2. June 1992.

Nuclear and Reactor Physics:

  1. J. R. Lamarsh, Introduction to Nuclear Reactor Theory, 2nd ed., Addison-Wesley, Reading, MA (1983).
  2. J. R. Lamarsh, A. J. Baratta, Introduction to Nuclear Engineering, 3d ed., Prentice-Hall, 2001, ISBN: 0-201-82498-1.
  3. W. M. Stacey, Nuclear Reactor Physics, John Wiley & Sons, 2001, ISBN: 0- 471-39127-1.
  4. Glasstone, Sesonske. Nuclear Reactor Engineering: Reactor Systems Engineering, Springer; 4th edition, 1994, ISBN: 978-0412985317
  5. W.S.C. Williams. Nuclear and Particle Physics. Clarendon Press; 1 edition, 1991, ISBN: 978-0198520467
  6. G.R.Keepin. Physics of Nuclear Kinetics. Addison-Wesley Pub. Co; 1st edition, 1965
  7. Robert Reed Burn, Introduction to Nuclear Reactor Operation, 1988.
  8. U.S. Department of Energy, Nuclear Physics and Reactor Theory. DOE Fundamentals Handbook, Volume 1 and 2. January 1993.
  9. Paul Reuss, Neutron Physics. EDP Sciences, 2008. ISBN: 978-2759800414.

See above:

Radiation Dosimetry