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Occupational Intakes of Radionuclides Part 1 - ICRP

Occupational Intakes of Radionuclides Part 1 - ICRP

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DRAFT REPORT FOR CONSULTATION<br />

position where the dosemeter is worn, and E(50) is the committed effective<br />

dose from internal exposure as assessed by:<br />

E ( 50)<br />

e j, inh ( 50)<br />

I j, inh <br />

ej,<br />

ing(<br />

50)<br />

<br />

j<br />

j<br />

where ej(50) is the dose coefficient (committed effective dose per unit intake,<br />

Sv Bq -1 ) <strong>of</strong> a radionuclide, integrated over 50 years after intake by inhalation<br />

(inh) and/or ingestion (ing). The intakes, Ij (Bq), may be for one or a number <strong>of</strong><br />

radionuclides.<br />

(60) The dose coefficient for intakes <strong>of</strong> radionuclides is the fundamental quantity<br />

recommended by <strong>ICRP</strong> for protection purposes. The Annual Limit on Intake (ALI)<br />

and the Derived Air Concentration (DAC) are derived parameters that can be useful in<br />

the control <strong>of</strong> exposures.<br />

(61) The ALI was defined in Publication 60 (<strong>ICRP</strong>, 1991, paragraph S30) as an<br />

intake (in Bq) <strong>of</strong> a radionuclide in a year which would lead to a committed effective<br />

dose <strong>of</strong> 20 mSv (0.02 Sv). The average annual limit on intake for workers would thus<br />

be:<br />

ALI <br />

j<br />

0.<br />

02<br />

e ( 50)<br />

j<br />

(62) The DAC is the activity concentration in air (in Bq m -3 ) <strong>of</strong> the radionuclide<br />

considered which would lead to an intake <strong>of</strong> an ALI assuming a sex-averaged<br />

breathing rate <strong>of</strong> 1.1 m 3 h -1 and an annual working time <strong>of</strong> 2000 h. Then the DAC is<br />

given by:<br />

ALI j<br />

DAC j <br />

2200<br />

(63) <strong>ICRP</strong> does not now give ALI values because it considers that for compliance<br />

with dose limits it is the total dose from external radiation as well as from intakes <strong>of</strong><br />

radionuclides that must be taken into account, as indicated above. It is, however,<br />

noted that the ALI concept can be useful in various practical situations, characterising<br />

the relative hazard <strong>of</strong> radiation sources to ensure that appropriate administrative<br />

controls are in place. ALI values can be easily calculated using the equations given in<br />

the previous paragraphs.<br />

41<br />

I<br />

j, ing<br />

2.3 Objectives <strong>of</strong> Monitoring<br />

(64) The purpose <strong>of</strong> monitoring for internal exposure to radionuclides is to verify<br />

and document that the worker is protected adequately against radiological risks, and<br />

that the protection afforded complies with legal requirements. Two types <strong>of</strong><br />

monitoring <strong>of</strong> internal exposures <strong>of</strong> workers can be identified: workplace monitoring<br />

and individual monitoring.

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