Wednesday, February 26, 2014

Terrestrial Gamma Radionuclides and Radiation Dose in Udupi District

1.    Introduction
The terrestrial sources of radiation can be divided into those that occur singly and those that are components of the three chains of radioactive series namely the uranium series, the thorium series and the actinium series. Among the singly occurring radionuclides Potassium-40 with half life of 1.3X109 years is the most prominent one and it is widely distributed in rocks and soil. 
            Uranium-238 and Thorium-232 and their daughters generate the bulk of natural ionising radiation in our environment.  Uranium-238 is the head of a series of 15 principal radionuclides .  It is the most abundant (99.28%) isotope of natural uranium and is found in all rocks and soil with varied concentration. The 238U decays through 234U and 230Th to 226Ra, which has a relatively long half life of 1628 years.  226Ra and its daughter products constitute an important part of natural radiation exposure.

            The other major source of terrestrial radiation is 232Th and its decay products. Thorium-232 is the only long lived radionuclide in its chain and is widely distributed in rocks and soil in varied concentration.

            The radioactive decay of 40K and radionuclides of 238U and 232Th series give rise to the terrestrial gamma rays.

In addition to the natural source of radiation some of the present day technological activities enhance the natural radiation exposure to human population. The production of electric power through oil and coal power stations release radio nuclides like Uranium, Thorium and K-40 mailnly due to escape of fly ash.
The coastal Karnataka is witnessing rapid industrialization and power generation activities by Nuclear as well as Thermal Power stations which are coming up in the region. There fore it is important to ensure that the impact of these scientific and industrial endeavors on the environment are kept minimum and systematic studies are under taken to safe guard the environment.
    This is the first systematic and comprehensive study in the Udupi District which is the Coastal District of Karnataka which consists of a number of beautiful beaches   and where a controversial Thermal Power plant is coming up.

2. Objectives

The  main objective of the present investigations are

  • To evaluate the gamma radiation dose to the population of Udupi district
  • To measure the concentrations of 226Ra, 232Th and 40K in soil/sand and
  • To calculate the contribution of cosmic radiation to the radiation dose received by the population

The data on above aspects would help in establishing a reliable data base on baseline level of radiation and distribution of different primordial radio nuclides for Udupi District and would help to understand the dynamics of natural radiation background of the region. This baseline data would also help in assessing, in future, the impact of our scientific and technological endeavors on the environment.



3.Area covered: Selection of Soil Samples:
·         Udupi District consists of three taluks namely Coondapur, Udupi and Karkala. Coondapur, Udupi are coastal taluks while Karkala is  hilly contains granite rocks.

·         Radiation is measured in 60 places in Udupi Taluk, 12 places in Karkala Taluk and  Places in Coondalpr taluk.
·         25 soil samples from Udupi Taluk,  6  soil samples from Karkala Taluk qand 6 soil samples from Coondapur Tauk  were selected .  The total extend is about 150 Km. The area covers sea shores some of them are very famous tourists spots, pilgrimage centres and hilly regions.  The are also covers the places where major Industries are coming up like Nandikoor near Padubidri and Brahmavar.


4 Experimental method:


4.1   Dosi meter
                   The gamma exposure rate in air were measured using a portable gamma level survey meter procured from Nucleonix Systems (Hyderabad). The instrument has an excellent flat energy response over a wide energy range (20 KeV to 2 Mev) with a sensitivity of  0 to 10,000. mR-1 and a reading accuracy of  10 mR to mR. It contains Halogen quenched G.M detector LND78017 length 280mm, diameter 25mm  and operating voltage 500 volts.

      The instrument was factory calibrated. The gamma radiation levels were measured at a height of 1m from the ground level. Several measurements were made in a single region so as to get a representative reading of gamma radiation level prevailing in the region. The radiation exposure levels were converted into absorbed dose in air using appropriate conversion factor (Nambi et al., 1986).

4.2

Sample processing
All samples were processed following the standard procedure (EML Procedure Manual, 1983). Soils were well mixed after removing extraneous materials such as roots, mat portions, pieces of stones and gravel. Samples were weighed and then dried in an oven at 105°C for 24 h and re-weighed to find the water content. After mixing thoroughly, the samples were shaken in a sieve shaker and particle sizes of <250 250="" 30d="" a="" allow="" and="" containers="" factions="" for="" in="" microns="" minimum="" ml="" obtained.="" of="" period="" plastic="" samples="" sealed="" sieved="" stored="" sup="" to="" were="">226
Ra to come into equilibrium with its daughters. Proper sealing was ensured by providing double seal to the cap of the container to avoid 222Rn escaping out.

4.3  226Ra, 232Th and 40K determination
The activities of 226Ra, 232Th and 40K were determined by gamma spectrometry employing a 41% relative efficiency n-type low background HPGe detector having a composite carbon window (Canberra, USA). This detector can used for the mesuremnent of gamma energies from 5 keV to 10 MeV.  The composite carbon window allows about  90% gamma energies to pass it through.  The detector was enclosed in a 10 cm thick graded lead shield (Model 747, Canberra, USA) to reduce the background. The Canberra DSA-1000 (which consists of HV bias supply, ADC and 16K MCA) and GENIE-2000 software were used for data acquisition and analyses. The detector efficiency calibration was performed using the IAEA quality assurance reference materials: RG U-238, RG Th-232, RG K-1 and SOIL-6. The standard materials and samples were taken in containers of same size and type so that detection geometry remained the same. Samples were counted long enough to reduce the counting error. The 226Ra activity was evaluated from the weighted mean of the activities of three photopeaks of 214Bi (609.3, 1129.3 and 1764.5 keV) after applying Compton corrections. In the case of 232Th one photopeak of 228Ac (911.2 keV) and two photopeaks of 208Tl (583.1 and 2614.5 keV) were used in the same way. The activity of 40K was derived from its 1460.8keV gamma line (Abani, 1994).


3. Results and Discussion:

                          Table 1

Terrestrial Radio Nuclides Concentration (Bq\Kg)  in the soil of Udupi District and Gamma Dose rate
Place
K-40
Th-232
Ra-226
Gamma Dose rate nGy\h
measured directly using gamma dose survy meter nGy\h
Gamma Dose rate calculated from radio nuclide activities nGy\h
1.Kodavoor
73.0
26±1.0
34.9±0.0
79
35
2.Cherkady
219.2
44.9±1.2
26.1±0.9
79
48
3.Kakkunje
128.8
43.6±1.3
42.9±1.1
105
52
4.Karje
493.5
14.8±0.8
6.1±0.7
105
32
5.Kukke Halli
108.6
24.8±0.9
19.7±0.7
105
29
6.Dupadakatte
124.5
51.7±1.3
44.2±1.0
88
57
7.Kemmannu
366.5
18.9±0.9
12.83±0.7
96
33
8.Barhmavar 9.Sugar Factory
89.9
25.28±0.9
29.4±0.8
88
33
10.Kallianpur
190.5
49.9±1.2
54.8±1.1
105
63
11.Pamboor
199.5
41.3±1.2
34.7±0.9
114
49
12.Shivally
183.8
38.9±1.1
55.1±1.1
123
57
13.Nejar
194.8
51.4±1.3
63.5±1.1
96
69
14.Tenkanidiyur
222.6
26.9±0.9
17.9±0.8
79
34
15.Hebri (Near Karje)
202.3
79.3±1.7
48.6±1.2
70
79
16.Yedthady
137.0
21.3±0.9
21.4±0.8
114
28
17.Kukkehalli North
119.7
28.1±0.9
23.0±0.7
123
33
18.Kokkarne
72.9
29.3±0.8
15.1±0.6
105
28
19.Hebri Nisargadama
254.1
47.2±1.2
30.8±0.9
105
53
20.Perampalli
92.8
40.7±1.2
48.9±1.0
123
51
21.Herror
105.1
27.0±0.8
43.5±0.8
88
41
22.Cherkady
256.6
53.4±1.4
26.2±1.0
79
55
23.Malpe Sand
231.7
2.31±0.5
2.6±0.4
70
12
24.Hoode sand
84.3
88.8±1.6
41.1±1.0
70
76
25.Nandikoor
171.1
6.9±1.6
21.8±1.0
88
21
26.Nakre
213.9
118.9±1.8
38.9±1.0
114
99
27.Ajekar
323.1
166.2±2.2
78.0±1.4
112
150
28.Karkala
230.6
60.9±1.3
53.9±1.3
114
71
29.Bailur
477.1
47.0±1.2
33.8±1.0
114
64
30.Nitte
190.6
37.1±1.1
28.4±0.9
70
43
31.Maravanthe Beach
57.4
1.6±0.6
1.2±0.5
53
40
32.Byndoor  Beach
155.5
62.1±0.3
19.7±0.9
61
53
33.Kambadakone
127.1±4.9
28.8±0.9
22.7±0.8
79
33
34.Tallur
179.3±5.6
48.3±1.1
46.9±0.9
79
38
35.Gangolli
119.3±4.5
18.6±0.8
18.6±0.7
114
25
36.Byndoor Hill
11.8±2.9
14.9±0.8
13.8±0.6
96
16



4.4 Natural radionuclides distribution in soil

The natural radionuclides activity in surface soils (0-5cm depth) of Udupi and Karkala  and Kundapur region are presented in Table 1. Results are presented region wise and range and mean value for each region as well as the overall range and mean values for the entire study region are also presented in the table. The activity of 226Ra is in the range 2.6. to 63.5. Bq kg-1 with a mean value of 30.91Bq kg-1, 232Th in the range 6.9. to 126 Bq kg-1 with a mean value of 30.19 Bq kg-1 and that of 40K in the range73  to 493 Bq kg-1 with a mean value of 180.8. Bq kg-1 in the surface (0-5cm) soils.  The results of radioactivity measurement in sand samples collected from sea shore  also showed similar variation as that observed in soil samples of the region. A comparison of the activities of different radionuclides observed in the present study with those reported for other environs showed that the activities of 226Ra, 232Th and 40K are comparable with those reported for other parts of India (Mishra and Sadasivan, 1971, Kamath et al., 1996) as well as values reported for world range and average (UNSCEAR 2000).

Gamma absorbed dose rates
The gamma absorbed dose rates in air measured using the plastic scintillometer, which includes both terrestrial and cosmic ray components, are presented in Table 1, column 5.  It can be seen that absorbed dose rates vary from 60… nGy h-1 to 158 nGy h-1, with a mean value of 91.31. nGy h-1. The dose rates were found to be more or less uniform in the entire study region with results of individual locations flucatuating around the mean value of the entire region. The mean value of dose rates prevailing in south west coast of India is comparable with the mean values of 80.7 nGy h-1 (Mishra and Sadasivan, 1971) and 88.7 nGy h-1 (Nambi et al., 1987) reported for different regions of India and also with the mean value 74 nGy h-1 (Siddappa et al., 1994) reported for environment of Coastal Karnataka region. The dose rates are also comparable with the world range (28-120 nGy h-1) and the average value (56 nGy h-1) reported for normal background areas (UNSCEAR, 1993).

            From the results of 226Ra, 232Th and 40K activities in soil (Tables 1) the gamma dose rates in air were calculated using the dose coefficients (nGy h-1 per Bq kg-1) 0.461, 0.623 and 0.0414 given in UNSCEAR (1993) for 226Ra sub-series, 232Th series and 40K, respectively and by assuming secular equilibrium between 238U and 226Ra. It may be noted that about 98% of the external dose from 238U series is delivered by 226Ra sub-series. Therefore, the disequilibrium between 226Ra and 238U, if any, does not affect  the dose estimation from the concentration of 226Ra. Therefore the dose rates derived from 226Ra are presented as that of 238U. Further, for a typical radiation field, the layer of soil which makes the predominant contribution to external gamma dose above the ground is about 30 cm thick (UNSCEAR, 1977). The results of these calculations are summarized in Table  (column 5).

            {The absorbed dose from 238U sereis varies in ….. to …. nGy h-1 with a mean value of …… nGy h-1. The dose rate due to 232Th series varies from ….. to …. nGy h-1 with a mean value of …… nGy h-1. Similarly, the minimum and maximum values of dose rates due to 40K are, respectively ….. nGy h-1 and …… nGy h-1, the mean value being …… nGy h-1. The dose delivered by these radionuclides, in total, range from ….. to ….. nGy h-1 with a mean value of 44.4 nGy h-1 (column 2). This mean value of total absorbed dose rate matches well with the world average value of 44.4 nGy h-1 reported in UNSCEAR (1988).

            The percentage contributions of 238U, 232Th and 40K to the external dose rates in air are given in column 6-8 of Table 5. The mean values are …… and ……% for 238U, 232Th and 40K, respectively. Mishra and Sadasivan (1971) have reported these percentage contribution in the order of 17.7, 33.6 and 48.7 due to 238U, 232Th and 40K, respectively for Indian environs. UNSCEAR (1982) has reported the world wide average values for the relative contributions from 238U, 232Th and 40K gamma dose rates in air to be about 25%, 40% and 35%, respectively. It is interesting to note that the contribution of 40K to the dose is significantly less in the region under present investigation.  (This calculation I shall add later)

            The correlation between the absorbed dose rates in air computed from the measured concentrations of 226Ra, 232Th and 40K and that measured directly using the scintillometer is shown in Table in the column 5. It should be noted that measured dose rates  includes both terrestrial and cosmic ray components whereas the calculated dose rates shown  is purely due to the activities of 226Ra, 232Th and 40K in soil.  The correlation  indicates that the overall mean cosmic ray dose rate, shown by the intercept on scintillometer axis, is ……nGy h-1. This is higher/lower/comparable with the value of 32 nGy h-1 reported in UNSCEAR (1993) as also with the value 31.96 nGy h-1 reported for India at sea level (Nambi et al., 1986). }

7.0             Conclusions





Gamma Absorbed Dose rates in Udupi Taluk
Sl No

Place

Exposure Rate
nGy/h
1
Physics Department
123
2.
College Ground
105
3
Kallianpur
105
4
Near Swarna River
105
5
Doopada Katte(Brahmavar)
88
6
Brahmavar( Brahmavar Chemicals)
88
7
UppinaKote       
96
8
Mabukala ( Near River)
61
9
Saligrama
70
10
Kota
79
11
Bannadi
79
12
Girike Mata
88
13
Saibra Katte
96
14
Barkur
96
15
Yedthady
114
16
Near Mandharthi
105
17
Mandharthi
96
18
Kadoor
88
19
Kokkarne
105
20
Sural
96
21
Amuje(Karje)
70
22
Kannaru(Near Karje)
105
23
Petri
114
24
Cherkadi
79
25
Ammuje (Near Karje)-2
70
26
Chantharu
88
27
Brahmavar
(Near West Cost Chemicals)
105
28
Kolalgiri
105
29
Tenkabettu
105
30
SubasNagar
114
31
Pajaka
114
32
Padubelle
114
33
Manasa
114
34
B.C Road
88
35
Manchakkal
96
36
Bantakkal
88
37
Shankarpura
105
38
Katpady
105
39
Nittur
105
40
Puttur
79
41
Kodavur
96
42
Malpe Beach
70
43
Malpe Beach(Water)
61
44
Malpe Beach(Road)
96
45
Tottam
88
46
Badanidiyur
79
47
Gujjar Bettu
70
48
Hoode Beach
70
49
Kemmannu
96
50
Kelarkalabettu
96
51
Kaup Light House
105
52
Kaup Highway
79
53
Uchila
114
54
Padubidri
70
55
Nandikur(Nagarjuna)
88
56
Hiriyadka
105
57
Athrady
114
58
Parkala
105
59
Manipal(End Point)
105
60
Perampalli
123


Absorbed Dose in Karkala Taluk


Sl No

Place

Exposure Rate
nGy/h
1.
Santhoor
88
2
Belman
96
3
Kedinge
88
4
Nitte
70
5
Attur Church
(Miraculous Pond)
158
6
Attur Hill
114
7
Anekere
88
8
Gomateshwara Hill
123
9
Kukkundoor
96
10
Jarkala
123
11
Bailur
114
12
Guddeyangadi
114