Radioprotection No 59-2 | Page 24

J . A . Corbacho et al .: Radioprotection 2024 , 59 ( 2 ), 80 – 87 83
Table 1 . Experimental activities measured with the LaBr 3 ( Ce ) detector mounted on the drone at various heights and for different measurement times .
Distance
Acquisition time
Photopeak
Gross area
Efficiency
Activity
Detection Limit
Relative difference
source — detector
( s )
( energy keV )
± uncertainty
( x10 – 5 )
± uncertainty
( MBq )
( measure / reference )
( m )
( MBq )
(%)
137 Cs ( 661.7 )
2830 ± 130
4.96
1.1 ± 0.1
0.12
– 99
1 60
2 60
4 300
10 300
60 Co ( 1173 )
3200 ± 100
3.31
60 Co ( 1332 )
3110 ± 70
3.02
1.6 ± 0.2
0.08
– 98
137 Cs ( 661.7 )
920 ± 70
0.0967
19 ± 3
3.6
– 75
60 Co ( 1173 )
1170 ± 60
0.0648
60 Co ( 1332 )
1210 ± 50
0.0593
32 ± 4
2.5
– 60
137 Cs ( 661.7 )
2420 ± 120
0.0239
40 ± 5
4.7
– 47
60 Co ( 1173 )
3100 ± 100
0.0161
60 Co ( 1332 )
3160 ± 70
0.0147
68 ± 8
3.6
– 15
137 Cs ( 661.7 )
580 ± 60
0.0036
64 ± 10
17
– 15
60 Co ( 1173 )
690 ± 40
0.0025
60 Co ( 1332 )
590 ± 40
0.0023
91 ± 12
16
13
8 9
< e d ¼ e e ð�m ar a dÞ
=
1 m
4pd 2 ; d > 1 :
; ; ð5Þ e 1m ; d ¼ 1
where e 1m is the experimental efficiency at a distance of 1m , m a is the mass-attenuation coefficient in air ( 0.661 keV : 0.07538 cm 2 / g ; 1173 keV : 0.05840 cm 2 / g ; 1332.5 keV : 0.05518 cm 2 / g ), r a is the air density : 0.012923 g / cm 2 , and d is the separation in the air between the source and the detector .
It is important to note that expression ( 5 ) is a simplification , as it does not consider other parameters that also influence detector efficiency , such as the angle of incidence of photons at distances beyond 1 m ( Ritter , 2021 ).
Detection limits have been determined using the L . Currie criteria ( Currie , 1968 ).
Table 1 shows the activity values , detection limits , and its comparison to the reference values obtained from the different measurements .
The measurements carried out at distances close to the container ( 1 – 2 m ) give lower activity values than reference values . These results were to be expected because the efficiency calibration used was for a point source and the size of the radioactive source is too large to be considered a point source . However , for the measurement carried out at a distance of 10 m between the container and the drone , the measured activity values are of the same order of magnitude as reference values , despite the relative difference between measured activity and the reference activity still being significant (~ 15 %). However , this is considered to be a very satisfactory result for the objectives of using this type of device for in situ measurements with short acquisition time and applying a simplification to determine the efficiency of the detector at distances greater than 1 m .
3.2 Radiological characterisation of phosphate sludge landfill
The study area chosen to carry out a radiological characterisation using the measurements provided by the drone system developed in this work was a former phosphate production plant located in the southeast of Spain ( 37.61 N ; �0.965 ). Today , process wastes are still present , consisting mainly of phosphate sludge . Between 2005 and 2006 , a detailed radiological study of these areas was carried out ( CSN , 2009 ). The study area consists of two parts . One , where the buildings were located ( now demolished ), with a total surface of 180 000 m 2 . The second area , where there are three phosphate sludge ponds and various phosphate waste drifts has a total surface of 150 000 m 2 . Both areas are at an elevation between 9 and 21 metres above mean sea level .
Measurements were taken in a grid of approximately 10 10 m over the phosphate sludge ponds . The flight altitude was 1 m . These are optimal conditions for a suitable in situ gamma spectrometry measurement , since most of the photon flux reaching the detector , which is located 1 m above the ground , comes from an area equivalent to a circle with a radius of 10 m ( ICRU , 1994 ). At each point , a 30 s measurement was taken . The efficiency calibration for an infinite plane source with a homogeneous distribution in depth was used to determine the activity levels for natural radionuclides : 40 K , 226 Ra ( from its daughter : 214 Pb and 214 Bi assuming they were in equilibrium with their parent radionuclide ) and 232 Th ( 228 Ac ). In the event of an emergency , the most appropriate distribution would be an infinite plane where the radionuclides have been deposited in the surface layer .
The MDA values for a 30 s acquisition time and 1 m flight altitude are of the order of : 40 K : 300 Bq / kg ; 214 Pb : 30 Bq / kg ; 214 Bi : 30Bq / kg ; 228 Ac : 40 Bq / kg .
The conversion factor from gross gamma counts to H *( 10 ) detailed in Section 2.3 was also used to measure the ambient dose equivalent rate H *( 10 ) throughout the area .
Furthermore , the H *( 10 ) values was also calculated from the activity measurements of the 40 K , 226 Ra and 232 Th natural radionuclides measured by the drone-based system . For this purpose , the terrestrial component of the H *( 10 ) was calculated using the following expression ( Lemercier et al ., 2018 ).