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1 IAEA-TECDOC-1000 Clearance
2 The IAEA does
3 The originating Section of this publication in the IAEA was: Waste Safety Section International Atomic Energy Agency Wagramerstrasse
4 FOREWORD It has long been recognized that the use of sources of radiation should be regulated. The recommended regulatory approach is based on a system of notification and authorization exemplified by the IAEA International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources (BSS). However, some types of radiation source do not need to be subject to regulatory control because they can only give rise to trivial radiation hazards. Such sources may be exempted or cleared from the requirements of regulatory control. Exemption applies to radiation sources which do not enter the regulatory control regime, while clearance
5 In preparing this publication EDITORIAL NOTE
6 INTRODUCTION CONTENTS 1.1. Background...
7 1. INTRODUCTION 1.1. BACKGROUND Many uses
8 1.2. OBJECTIVE The objective of this report is to provide guidance on translating the principles of exemption from regulatory control into practice
9
10 TABLE
11 TABLE
12
13 In the case of discharge of liquid and gaseous effluents, the authorization may include discharge limits (i.e. total activity, concentration) and provisions to control the discharges (e.g. release rate). Control is carried out at the point of discharge and surveillance is performed in
14 equivalent which takes account of both the probability of incurring a dose and the detriment associated with that dose if it were to be received. It has been suggested in ICRP 60 [3] that
15 after that time.
16 conditions
17 4. RADIATION DOSE ASSESSMENT
18 TABLE II BASIC RADIOLOGICAL DATA FOR RADIONUCLIDES OF INTEREST Radionuclides H-3 C-14 Na-22 Na-24 P-32 S-35 Cl-36 K-42 Ca-45 Ca-47 Cr-51 Fe-59 Co-57 Co-58 Ga-67 Se-75 Sr-85 Sr-89 Y-90 Mo-99 Tc-99 Tc-99m In-Ill I- 123 I Xe-127 Xe-133 Pm-147 Er-169
19 cases. The transformation of tritium gas to tritiated water is slow in the environment. This requires consideration
20 of radionuclides through the terrestrial foodchains; inhalation of radionuclides transferred back into
21 water.
22 intrusion, while in other cases little or no control is exercised and intrusion could occur soon after
23 TABLE III. DERIVED GENERIC CLEARANCE LEVELS FOR AIRBORNE RELEASES Radionuclide H-3 Annual release rate (Bq C-14 Na-22 Na-24 P-32 S-35 CI-36 K-42 Ca-45 Ca-47 Cr-51 Fe-59 Co-57 Co-58 Ga-67 Se-75 Sr-85 Sr-89
24 Table III. (cont.) Radionuclide Y-90 Annual release rate (Bq a' 1 ) 1 x 10' Mo-99 1 x 10" Tc-99 Tc-99m 1 x x 10" In x Xe-127 Xe-133 Pm-147 Er-169 Au-198 Hg-197 Hg-203 Tl-201 Ra-226 Th-232
25 TABLE
26 TABLE IV. (cont.) Radionuclide Pm-147 Annual release rate (Bq a 1 ) 1 x 10'" Er Au-198 Hg-197 Hg-203 Tl-201 Ra-226 Th-232
27 rate
28 5.3. GENERIC CLEARANCE LEVELS
29 clearance values derived using more appropriate local
30 where: C, = the proposed release rate, Bq a" 1 or concentration Bq g~' of radionuclide i in the waste; C
31 Appendix
32 Appendix
33 where:
34 (B.4) where: C A is the annual average concentration of the radionuclide in air at the point of interest (Bq m" 3 ) R, nh is the inhalation rate (m 3 a" 1 ) DF mh is the dose coefficient for intake by inhalation (Sv Bq"').
35 E ing. p = C p,.h p.df ingi (B.7) where: C p., is the concentration of radionuclide i in food p at the time of intake (Bq kg" 1 ) H p is the consumption rate for food p (kg a" 1 ) DF, ngl
36 TABLE B.I. REPRESENTATIVE CRITICAL GROUP CONSUMPTION RATES OF DIFFERENT FOODS Food Crops (kg a" 1 ) Milk (1 a ') Meat (kg a"') Water
37 TABLE B.II. EXTERNAL
38 TABLE B.II (cont.) Radionuclide Dose coefficient for intake H-3 (c) C-14 (c) Na-22 Na-24 P-32 S-35 Cl-36 K-42 Ca-45 Ca-47 Cr-51 Fe-59 Co-57 Co-58 Ga-67 Se-75 Sr-85 Sr-89 Y-90 Mo-99 Tc-99 Tc-99m In Xe-127 Xe-133 Pm-147 Er-169 Au-198 Tl-201 Hg-197 Hg-203 Ra-226 Th-232
39 TABLE
40 B.2. LIQUID DISCHARGES B.2.1. Release
41
42 Where: q w is the flow rate in m 3 s" 1 B is the width of the river in m
43 This is the total concentration in the water and is the sum of the dissolved and suspended sediment sorbed radionuclides.
44 Therefore,
45
46 used in the calculations of the generic clearance values are given in Tables B.II and B.IV. The important exposure pathways for each radionuclide are indicated on Table IV of the main text. Tritium is treated separately (see Section B.3). In each case the generic value given in Table
47 TABLE B.IV. PARAMETERS USED FOR RELEASES TO RIVERS Radionuclide C-14 Na-22
48 From Section B.I.I, the value of X at 100 m from unit discharge to atmosphere is 1.3 x 10 4 Bq m\ therefore at 100 m: 1.3 x It)" x lo' 3
49 DF
50 Appendix
51 TABLE C.II. COLLECTIVE DOSES FOR RELEASES OF RADIONUCLIDES TO WATER BODIES Radionuclide Clearance level (Bq a 1 ) H-3 C-14 P-32 S-35 Cr-51 Fe-59 Co-58 Sr Th-232 1
52 REFERENCES
53 [18] LAWSON, G., COOPER, J.R., McCOLL, N.P., Radiological Impact of Routine Discharges from UK Civil Nuclear Sites, National Radiological Protection Board, Chilton,
54 CONTRIBUTORS TO DRAFTING AND REVIEW Alvarez, A. Asikainen,
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