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It has been suggested that Radiation Exposure Monitoring be merged into this article. (Discuss) Proposed since November 2012.

Radiation dosimetry is the measurement and calculation of the radiation dose received by matter and tissue resulting from the exposure to indirect and direct ionizing radiation. It is a scientific sub-specialty in the fields of health physics and medical physics that is focused on the calculation and analysis of internal (Internal dosimetry) and external doses. Internal dose is calculated from a variety of physiological techniques, whilst external dose is usually measured with a dosimeter or inferred from other radiation instruments.

Dosimetry is normally applied to occupational radiation workers, where a radiation dose is expected, but regulatory levels must not be exceeded. It is also used where radiation is unexpected, such as in the aftermath of the Chernobyl or Fukishima radiological release incidents, where the public dose is measured and calculated from a variety of indicators such as ambient measurements of radiation and radioactive contamination. In both cases the information is used to calculate any likely detrimental health effects.

Measuring dose

External dose

There are several ways of measuring doses from ionizing radiation. People in occupational contact with radioactive substances or who may be exposed to radiation routinely carry personal dosimeters. These are specifically designed to record and indicate the dose received. Traditionally these were badges containing photographic film (film badge dosimeter), which would be chemically developed following exposure to indicate the total dose received. Film badges have now been largely replaced with other devices such as the TLD badge which uses Thermoluminescent dosimetry or optically stimulated luminescence (OSL) badges.

A number of other electronic devices have come into general use using semiconductor detection technology. These are worn as badges, but can give an indication of instantaneous dose rate, and can give an audible and visual alarm if a rate or a total integrated dose is being exceeded. These are particularly useful for real-time monitoring of dose rate where exposure time is likely to be short, and a rapid analysis of dose received is required. They may be used as stand-alone or as a supplement to such as a TLD badge.

In certain circumstances dose can be inferred from readings taken by fixed instrumentation in an area in which the person concerned has been working. This would generally only be used if personal dosimetry had not been issued, or a personal dosimeter has been damaged or lost. Such calculations would take a pessimistic view of the likely received dose.

Internal Dose

Internal dosimetry is used to evaluate the radiation dose of the intake of radionuclides into the human body.

Measures of Dose

There are a number of different measures of radiation dose, including absorbed dose (D) measured in grays (Gy), Equivalent dose (H) measured in sieverts (Sv), Effective dose (H) (also measured in sieverts) and Kerma (K) measured in grays, along with dose area product (DAP) and dose length product (DLP). Each measure is often simply described as ‘dose’, which can lead to confusion. Non-SI units are still used, particularly in the USA, where dose is often reported in rads and dose equivalent in rems. By definition, 1 Gy = 100 rad and 1 Sv = 100 rem.

The fundamental measure of the biological effect of ionising radiation is the absorbed dose (D), which is defined as the mean energy imparted (dE) per unit mass (dm) of material (D = dE/dm) The SI unit of absorbed dose is the gray (Gy) defined as one joule per kilogram. Absorbed dose, as a point measurement, is suitable for describing localised (i.e. partial organ) exposures such as tumour dose in radiotherapy. It may be used to estimate stochastic risk provided the amount and type of tissue involved is stated. Localised diagnostic dose levels are typically in the 0-50 mGy range. At a dose of 1 milligray (mGy) of photon radiation, each cell nucleus is crossed by an average of 1 liberated electron track.

Equivalent Dose

The absorbed dose required to produce a certain biological endpoint varies between different types of radiation, such as photons, neutrons or alpha particles. This is taken into account by the equivalent dose (H), which is defined as the mean dose to organ T by radiation type R (D_T,R), multiplied by a weighting factor w_R designed to takes into account varying biological effectiveness (RBE) of the radiation type, i.e. for the same absorbed dose in Gy, alpha particles are 20 times as biologically potent as X or gamma rays. Note that the earlier measure of ‘dose equivalent’ is not organ averaged. Equivalent dose is primarily designed for estimation of stochastic risks from radiation exposures. Stochastic effects, which include cancer and hereditary effects are probabilistic in nature, theoretically resulting from mutation to a single cell. As dose is averaged over the whole organ; equivalent dose is rarely suitable for evaluation of acute radiation effects or tumour dose in radiotherapy. In the case of estimation of stochastic effects, assuming a linear dose response, this averaging out should make no difference as the total energy imparted remains the same.

Effective dose

It is difficult to compare the stochastic risk from localised exposures of different parts of the body (e.g. a chest x-ray compared to a CT scan of the head), or to compare exposures of the same body part but with different exposure patterns (e.g. a cardiac CT scan with a cardiac nuclear medicine scan). One way to avoid this problem is to simply average out a localised dose over the whole body. The problem of this approach is that the stochastic risk of cancer induction varies from one tissue to another. The effective dose (E) is designed to account for this variation by the application of specific weighting factors for each tissue (W_T). Effective dose provides the equivalent whole body dose that gives the same risk as the localised exposure. It is defined as the sum of equivalent doses to each organ (H_T), each multiplied by its respective tissue weighting factor (w_T).

Weighting factors are calculated by the International Commission for Radiological Protection (ICRP), based on the risk of cancer induction for each organ and adjusted for associated lethality, quality of life and years of life lost. Organs that are remote from the site of irradiation will only receive a small equivalent dose (mainly due to scattering) and therefore contribute little to the effective dose, even if the weighting factor for that organ is high. Effective dose is used to estimate stochastic risks for typical examinations for a ‘reference’ person. It is not suitable for estimating stochastic risk for individual exposures to individual patients and should never be used to assess acute radiation effects.

Dose versus activity

Radiation dose refers to the amount of energy deposited in matter and/or biological effects of radiation, and should not be confused with the unit of radioactive activity (becquerel, Bq). Exposure to a radioactive source will give a dose which is dependent on the activity, duration of exposure, energy of the radiation emitted, distance from the source and shielding. The equivalent dose is then dependent upon the weighting factors above. Dose is a measure of deposited dose, and therefore can never go down—removal of a radioactive source can only reduce the rate of increase of absorbed dose, never the total absorbed dose.

The worldwide average background dose for a human being is about 3.5 mSv per year , mostly from cosmic radiation and natural isotopes in the earth. The largest single source of radiation exposure to the general public is naturally-occurring radon gas, which comprises approximately 55% of the annual background dose. It is estimated that radon is responsible for 10% of lung cancers in the United States.

Calibration standards

Because the human body is approximately 70% water and has an overall density close to 1 g/cm, dose measurement is usually calculated and calibrated as dose to water.

National standards laboratories such as the NPL provide calibration factors for ionization chambers and other measurement devices to convert from the instrument's readout to absorbed dose. The standards laboratories operate a Primary Standard, which is normally calibrated by absolute calorimetry, the warming of substances when they absorb energy. A user sends their Secondary Standard to the laboratory, where it is exposed to a known amount of radiation (derived from the Primary Standard) and a factor is issued to convert the instrument's reading to that dose. The user may then use their Secondary Standard to derive calibration factors for other instruments they use, which then become tertiary standards, or field instruments.

The NPL in the UK operates a graphite-calorimeter for absolute photon dosimetry. Graphite is used instead of water as its specific heat capacity is one-sixth that of water and therefore the temperature rises in graphite are 6 times more than the equivalent in water and measurements are more accurate. Significant problems exist in insulating the graphite from the laboratory in order to measure the tiny temperature changes. A lethal dose of radiation to a human is approximately 10–20 Gy. This is 10-20 joules per kilogram. A 1 cm piece of graphite weighing 2 grams would therefore absorb around 20–40 mJ. With a specific heat capacity of around 700 J·kg·K, this equates to a temperature rise of just 20 mK.

Dosimeters in radiotherapy (linear particle accelerator in external beam therapy) are routinely calibrated using ionization chambers or the new and more accurate diode technology.

Medical dosimetry

Medical dosimetry is the calculation of absorbed dose and optimization of dose delivery in radiation therapy. It is often performed by a professional medical dosimetrist with specialized training in the field. In order to plan the delivery of radiation therapy, the radiation produced by the sources is usually characterized with percentage depth dose curves and dose profiles measured by medical physicists.

Radiation exposure monitoring

Records of legal dosimetry results are usually kept for a set period of time, depending upon the legal requirements of the nation in which they are used.

medical radiation exposure monitoring is the practice of collecting dose information from radiology equipment and using the data to help identify opportunities to reduce unnecessary dose in medical situations.

See also

• Health physics
• Dosimeter
• Radiation dose reconstruction

References

1. ^ International Commission on Radiation Units and Measurements (ICRU).Options for Characterizing Energy Deposition. Journal of the ICRU Vol 11 No 2 (2011) Report 86
2. Feinendegen LE. The cell dose concept; potential application in radiation protection. 1990 Phys. Med. Biol. 35 597
3. "The 2007 Recommendations of the International Commission on Radiological Protection". Annals of the ICRP. ICRP publication 103. 37 (2–4). 2007. ISBN 978-0-7020-3048-2. Retrieved 17 May 2012.
4. UNSCEAR-2008 Annex A page 40, table A1, retrieved 2011-7-20

External links

• Nucleonica Wiki on Dosimetry & Shielding
• Nucleonica website
• The Karlsruhe Nuclide Chart
• Tim Stephens and Keith Pantridge, 'Dosimetry, Personal Monitoring Film' (a short article on Dosimetry from the point of view of its relation to photography, in Philosophy of Photography, volume 2, number 2, 2011, pp. 153–158.)

• Articles to be merged from November 2012
• Radiobiology
• Radiation therapy
• Nuclear physics
• Medical physics