epr-method (2003) - IAEA Publications - International Atomic Energy ...

Table A8-I D Values [TBq]
Sources and material 105
Radionuclide
106
D 1
107
D 2
H-3 UL 108 2.E+03 109
C-14 2.E+05 5.E+01
P-32 1.E+01 2.E+01
S-35 4.E+04 6.E+01
Cl-36 3.E+02 2.E+01 110
Cr-51 2.E+00 5.E+03
Fe-55 UL 8.E+02
Co-57 7.E-01 4.E+02
Co-60 3.E-02 3.E+01
Ni-63 UL 6.E+01
Zn-65 1.E-01 3.E+02
Ge-68 7.E-02 2.E+01
Se-75 2.E-01 2.E+02
Kr-85 3.E+01 2.E+03 111
Sr-89 2.E+01 2.E+01
Sr-90 (Y-90) 112 4.E+00 1.E+00
Y-90 5.E+00 1.E+01 113
Y-91 8.E+00 2.E+01
Zr-95
(Nb-95m/Nb-95) 112 4.E-02 1.E+01
Nb-95 9.E-02 6.E+01
Mo-99 (Tc-99m) 112 3.E-01 2.E+01 113
Tc-99m 7.E-01 7.E+02 113
Ru-103 (Rh-103m) 112 1.E-01 3.E+01
105 The amount of material if not controlled in the public domain (i.e. allowing removal of shielding or allowing dispersal)
that could give rise to exposure resulting in a permanent injury that would decrease the quality of life. Appendix 18 provides
a plain language statement of the risk to the public for an uncontrolled dangerous source.
106 This is for external exposure and applies to both dispersible and non-dispersible materials. It is the amount of material
without shielding that, if carried in a pocket for 10 hours could result in a severe injury (deliver 25 Gy at 2.0 cm in 10 hours)
except where the amount needed would be too big to put in a pocket for which it is the amount that could be life threatening
if people are near it for a long time (days–weeks) (deliver 0.01 Gy/h at 1 m). Both gamma emissions and bremsstrahlung
from beta and conversion electrons were considered. They were based, except for neutron sources, on absorbed dose
coefficients from Ref. [48].
107 This is the quantity of material that if dispersed could deliver long term doses that could result in permanent injuries that
decrease the quality of life. Airborne dispersal by fire or explosion, inadvertent ingestion and intentional contamination of
water was considered. For low LET emitters, quantities that can result in 6 Gy to the lung, 1 Gy to the red bone marrow, or 5
Gy to the thyroid delivered over two days [2, 3, 47] following intake and for high LET emitters (e.g. alpha) quantities that
can deliver 25 Gy to the lung over one year [46] were considered to deliver long term doses that are at the threshold for the
onset of permanent injuries that would decrease the quality of life. The absorbed doses from intake were, except for Cf-252,
based on absorbed dose coefficients from Ref. [48].
108 UL - Unlimited quantity - Emergency planning for dealing with radiological consequences is not recommended.
109 Assumes skin absorption doubles the absorbed dose from intake via inhalation.
110 Emergencies involving these amounts of these radionuclides may result in airborne concentrations exceeding the
immediate danger to life or health (IDLH) [35] concentration for chemical toxicity. Emergency arrangements to deal with the
chemical toxicity and perceived risks may be warranted.
111 The amount of Kr-85 that can deliver 1 Gy from submersion in 0.5 hours if 100% is released into a 300m 3 room – the
exposure scenario from Ref. [42].
112 It was assumed that this source is up to 10 years old at the time of the emergency and that the D value is the quantity of the
parent remaining at the time of the emergency. The D values were calculated considering both the parent and important decay
products that are present after up to 10 years (radionuclide shown in parenthesis). Decay products with a half-life of less than
1 year can be assumed to be in equilibrium with their parents.
113 Not a long term concern as it is short lived (has a half life of less than about 7 days) and within one month (and in most
cases much less), the radiological hazard will be greatly diminished.
182