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Safety_Series_041_1975 - gnssn - International Atomic Energy ...

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Please see http://www.ns-iaea.org/standards/<br />

SECTION VIII 31<br />

The dim ension o f the dose com m itm ent is absorbed dose o r<br />

d ose -equivalent, depending upon whether it is the dose rate<br />

D(t) o r the dose equivalent rate H(t) that is integrated o v e r<br />

tim e.<br />

The population ov e r which the dose rate is averaged may<br />

be any population o f in terest; e.g . the whole w orld population<br />

o r the critic a l group with regard to the given sou rce of<br />

exp osu re. An extrem e case is the integration o f the dose<br />

rate fo r a single individual, in which case the dose c o m ­<br />

m itm ent is sim ply his expected total future d ose, e .g . per<br />

unit intake of a sp ecified radionuclide. When the dose<br />

com m itm ent is calcu lated, the tissue o r organ fo r which the<br />

dose rate is integrated must be indicated.<br />

If the sou rce is constant in tim e, the equilibrium dose<br />

p er any sp ecified unit of tim e is n u m erically equal to the<br />

dose com m itm ent p er unit tim e of the p ractice causing the<br />

exposu re. F or exam ple, the annual dose in equilibrium is<br />

equal to the dose com m itm ent of one year of the operation<br />

causing the exposu res.<br />

DOSE-EQUIVALENT<br />

808. The d ose-equ ivalen t fo r a given type of radiation and at a<br />

given location in the body is n u m erically equal to the p r o ­<br />

duct of the absorbed dose in rads fo r that radiation at that<br />

p osition , and appropriate m odifying fa ctors such as the<br />

quality fa cto r, which accounts fo r the d ifferen ce in the<br />

lin ear en ergy tra n sfer of different d irectly ionizing ra d ia ­<br />

tions at the location of in terest. The sp ecia l unit is the rem .<br />

EM ERGENCY SURVEY<br />

809. An em ergen cy su rvey is a su rvey related to an accident<br />

involving loss o f con trol o v e r radiation sou rces o r ra d io ­<br />

active m aterial which could give rise to external radiation<br />

exposure levels o r intakes o f radioactive m aterials in ex cess<br />

o f those perm itted in the applicable regulations fo r n orm al<br />

operation.

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