Occupational Intakes of Radionuclides Part 1 - ICRP
Occupational Intakes of Radionuclides Part 1 - ICRP
Occupational Intakes of Radionuclides Part 1 - ICRP
You also want an ePaper? Increase the reach of your titles
YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.
1435<br />
1436<br />
1437<br />
1438<br />
1439<br />
1440<br />
1441<br />
1442<br />
1443<br />
1444<br />
1445<br />
1446<br />
1447<br />
1448<br />
1449<br />
1450<br />
1451<br />
1452<br />
1453<br />
1454<br />
1455<br />
1456<br />
1457<br />
1458<br />
1459<br />
1460<br />
1461<br />
1462<br />
1463<br />
1464<br />
1465<br />
1466<br />
1467<br />
1468<br />
1469<br />
1470<br />
1471<br />
1472<br />
1473<br />
1474<br />
1475<br />
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.