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If the source of radiation is inside our body, we say, it is **internal exposure**. The intake of radioactive material can occur through various pathways such as ingestion of radioactive contamination in food or liquids, inhalation of radioactive gases, or through intact or wounded skin. Most radionuclides will give you much more radiation dose if they can somehow enter your body, than they would if they remained outside. For internal doses, we first should distinguish between intake and uptake. Intake means what a person takes in. Uptake means what a person keeps.

When a radioactive compound enters the body, the activity will decrease with time, due both to **radioactive decay** and to **biological clearance**. The decrease varies from one radioactive compound to another. For this purpose, the biological half-life is defined in radiation protection.

The **biological half-life** is the time taken for the amount of a particular element in the body to decrease to half of its initial value due to elimination by biological processes alone, when the rate of removal is roughly exponential. The biological half-life depends on the rate at which the body normally uses a particular compound of an element. Radioactive isotopes that were ingested or taken in through other pathways will gradually be removed from the body via bowels, kidneys, respiration and perspiration. This means that a radioactive substance can be expelled before it has had the chance to decay.

As a result, the **biological half-life** significantly influences the **effective half-life** and the overall dose from internal contamination. If a radioactive compound with **radioactive half-life** (t_{1/2}) is cleared from the body with a biological half-life t_{b}, the effective half-life (t_{e}) is given by the expression:

As can be seen, the biological mechanisms always decreases the overall dose from **internal contamination**. Moreover, if t_{1/2} is large in comparison to t_{b}, the effective half-life is approximately the same as t_{b}.

For example, tritium has the biological half-life about 10 days, while the radioactive half-life is about 12 years. On the other hand, radionuclides with very short radioactive half-lives have also very short effective half-lives. These radionuclides will deliver, for all practical purposes, the total radiation dose within the first few days or weeks after intake.

For tritium, the **annual limit intake** (ALI) is 1 x 10^{9} Bq. If you take in 1 x 10^{9} Bq of tritium, you will receive a whole-body dose of 20 mSv. The **committed effective dose**, E(𝜏), is therefore 20 mSv. It does not depend whether a person intakes this amount of activity in a short time or in a long time. In every case, this person gets the same whole-body dose of 20 mSv.

## Committed Effective Dose

In radiation protection, the **committed dose** is a dose quantity that measures the stochastic health risk due to an **intake of radioactive material** into the human body. **Commited dose** is given the symbol **E(𝜏)**, where 𝜏 is the integration time in years following the intake. The SI unit of **E****(****𝜏****)** is the **sievert** (Sv) or but rem (roentgen equivalent man) is still commonly used (**1 Sv = 100 rem**). Unit of sievert was named after the Swedish scientist Rolf Sievert, who did a lot of the early work on dosimetry in radiation therapy.

**Committed dose** allows to determine the biological consequences of irradiation caused by radioactive material, that is inside our body. A committed dose of 1 Sv from an internal source represents the same effective risk as the same amount of effective dose of 1 Sv applied uniformly to the whole body from an external source.

The ICRP defines two dose quantities for individual committed dose.

**Committed Effective Dose**

According to the ICRP, the committed effective dose, E(𝜏) is defined as:

*“The sum of the products of the committed organ or tissue equivalent doses and the appropriate tissue weighting factors (w*_{T}*), where *𝜏* is the integration time in years following the intake. The commitment period is taken to be 50 years for adults, and to age 70 years for children.” *

**Committed Equivalent Dose**

According to the ICRP, the committed equivalent dose, H_{T}(𝜏) is defined as:

*“The time integral of the equivalent dose rate in a particular tissue or organ that will be received by an individual following intake of radioactive material into the body by a Reference Person, where *𝜏* is the integration time in years.”*

Special Reference: ICRP, 2007. The 2007 Recommendations of the International Commission on Radiological Protection. ICRP Publication 103. Ann. ICRP 37 (2-4).

## Annual Limit on Intake – ALI

In the assessment of committed effective doses for workers, intakes of radioactive material are controlled by the **Annual Limit on Intake (ALI)** defined by the ICRP, and expressed in units of activity (becquerels or curies).

The ALI was defined in by the ICRP in Publication 60 (ICRP, 1991b, paragraph S30) as:

*“the activity intake (Bq) of a radionuclide which would lead to an effective dose corresponding to the annual limit E*_{limit;w}*, under the expectation that the worker is exposed to only this radionuclide.”*

The ALI of radionuclide j is then:

where e(50) is the corresponding reference **committed effective dose coefficient** in (Sv/Bq). This dose coefficient, *e*(T), is determined by the radiotoxicity of a nuclide, and it accounts for radiation and tissue weighting factors, metabolic and biokinetic information.

See also: ICRP, 1994. Dose Coefficients for Intakes of Radionuclides by Workers. ICRP Publication 68. Ann. ICRP 24 (4).

The Commission recommended in Publication 60 that the ALI should be based on the dose limit of **E**_{limit;w}** = 0.020 Sv** in a year, with no time averaging. For members of the public **E**_{limit;w}** = 0.001 Sv** is the recommended value.

As an example, let assume an intake of radioactive tritium. For tritium, the annual limit intake (ALI) is 1 x 10^{9} Bq. If you take in 1 x 10^{9} Bq of tritium, you will receive a whole-body dose of 20 mSv. Note that, the biological half-life about 10 days, while the radioactive half-life is about 12 years. Instead of years, it takes a couple of months until the tritium has been pretty well eliminated. The **committed effective dose**, E(𝜏), is therefore 20 mSv. It does not depend whether a person intakes this amount of activity in a short time or in a long time. In every case, this person gets the same whole-body dose of 20 mSv.

For ^{131}I, ICRP has calculated that if you inhale 1 x 10^{6} Bq (ALI for ^{131}I), you will receive a thyroid dose of HT = 400 mSv (and weighted whole-body dose of 20 mSv).

## Derived Air Concentration – DAC

Concentrations of radioactive materials in air are limited by the Derived Air Concentration (DAC), which are derived from the ALI. The DAC is the activity concentration in air in units of Bq/m^{3} of the radionuclide considered, which would lead to an intake of an ALI (Bq) assuming a gender-averaged breathing rate of 1.1 m^{3}/h and an annual working time of 2000 h (an annual air intake of 2200 m^{3}).

The DAC was defined in by the ICRP in Publication 60 (ICRP, 1991b, paragraph S30) as:

*“Derived air concentration equals to the annual limit on intake, ALI, (of a radionuclide) divided by the volume of air inhaled by a Reference Person in a working year (i.e., 2.2×10*^{3}* m*^{3}*). The unit of DAC is Bq/m*^{3}*.”*

Special Reference: ICRP, 2007. The 2007 Recommendations of the International Commission on Radiological Protection. ICRP Publication 103. Ann. ICRP 37 (2-4).

Therefore, if we divide the ALI by 2200 m^{3}, we will get the DAC in Bq/m^{3}. For example, the ALI of iodine-131 is 1 x 10^{6} Bq. The corresponding DAC will be 1 000 000/2400 = 417 Bq/m^{3}.

The DAC of radionuclide j is given by:

If a worker breathes air containing radioactive material at a concentration of 1 DAC for one hour, then the worker has been exposed to 1 DAC.hr.

See also: Airborne Contamination

### Occupational Exposure – Effective Dose

In most situations of occupational exposure the effective dose, E, can be derived from operational quantities using the following formula:

The **committed dose** is a dose quantity that measures the stochastic health risk due to an **intake of radioactive material** into the human body. Since the operational dose limit of 20 mSv applies to the sum of the internal and external exposures, if a worker has some external dose, the ALI must be modified or offset to account for the external dose. For example, assume the worker has 10 mSv from external sources of radiation. Only 10 more mSv are allowed from internal radiation before the worker reaches the occupational whole body limit.

See also: Dose Limits