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2012| January-March | Volume 35 | Issue 1
Online since
May 6, 2013
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ORIGINAL ARTICLES
Radiological impact of soil as a source of building material
Francis Otoo, Emmanuel Ofori Darko, Geoffrey Emi-Reynolds, Aba Bentil Andam, Oscar Kwaku Adukpo
January-March 2012, 35(1):22-28
DOI
:10.4103/0972-0464.111406
The radiological hazards associated with naturally occurring radioactive materials in soil samples from different geological locations have been studied using gamma spectrometry. The average activity concentration of
226
Ra,
232
Th, and
40
K were (16.4-74.6 Bq/kg), (12.0-44.7 Bq/kg), and (215.4-498.6 Bq/kg). The highest values of
226
Ra and
232
Th occurred in Dodowa and Oyibi respectively. The
40
K recorded the highest activity concentration of 498.6 Bq/kg, measured in soil from McCarthy Hills. The radium equivalent activity (Ra
eq
; 46.9-135.7 Bq/kg), the internal hazards index (H
in
; 0.29-0.52) the external hazard index (H
ex
; 0.22-0.37), the absorbed dose rate in air (23.3-75.8 nGy/h), and the annual effective dose (E
T
) (44.4-79.4 uSv/y) were evaluated to assess the radiation hazard to the populace living in dwellings made of these soil as a building material. The results obtained were found to be within the acceptable limits for public exposure control recommended by the European Commission, International Commission on Radiological Protection, and Organization for Economic Cooperation and Development-Nuclear Energy Agency.
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Study on natural radioactive elements in soil and rock samples around Mandya district, India
BC Shivakumara, L Paramesh, TS Shashikumar, MS Chandrashekara
January-March 2012, 35(1):29-33
DOI
:10.4103/0972-0464.111407
Context:
The soil is a complex mixture of different compounds and rocks. In the natural environment, it is an important source of exposure to radiation due to naturally occurring, gamma emitting radionuclides which include
226
Ra,
232
Th and
40
K present in the soil.
Aims:
The study of distribution of these radionuclides in soil and rock is of great importance for radiation protection and measurements.
Materials and Methods:
The activity concentrations of
226
Ra,
232
Th, and
40
K in soil and rock samples collected in Mandya District, Karnataka state, India have been measured by gamma ray spectrometry.
Results:
The average activity concentrations of
226
Ra,
232
Th, and
40
K (Bq/kg) are found to be 40.2, 62.3, and 317.5 Bq/kg, respectively, in soil samples and 30.5, 34.4, and 700.2 Bq/kg, respectively, in rock samples.
Conclusion:
The concentrations of radionuclides in soil samples are found to higher than in rock samples. The concentrations of radionuclides in soil and rock samples in the study area are slightly higher than Indian average and world average values
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The derived radiological parameters associated with beach mineral sand deposits prevail in the south west coastal regions of India
Deva Sigamony Deva Jayanthi, Chavarachirayil Govindan Manian, Subramania Pillai Perumal
January-March 2012, 35(1):4-8
DOI
:10.4103/0972-0464.111402
The distribution of natural radioactivity in beach sand samples collected from naturally high background radiation areas of south west coast of Tamil Nadu in India is studied by gamma spectrometry. The activity concentration of radionuclide collected from the study area ranges from 18.9 ± 4.6 Bq/kg to 260.5 ± 29.4 Bq/kg for
226
Ra, 534.5 ± 34.0 Bq/kg to 2961.4 ± 33.7 Bq/kg for
232
Th, and 40.6 ± 7.2 Bq/kg to 148.7 ± 17.9 Bq/kg for
40
K. The measured activity of
226
Ra and
232
Th in soil samples collected from the study area is higher than the activity of
40
K. The external hazard index, internal hazard index, absorbed dose rate, and annual effective dose equivalent are calculated and tabulated. It is found that all the evaluated values are higher than the safe limit. The annual effective dose of radiation ranges from 0.41 mSv to 2.35 mSv due to naturally occurring radionuclide.
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2,433
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EDITORIAL
The new dose limit for the lens of the eye and its implications
BC Bhatt
January-March 2012, 35(1):1-3
DOI
:10.4103/0972-0464.111401
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NEWS AND INFORMATION
Basis for the ICRP dose limits
Pushparaja
January-March 2012, 35(1):55-56
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445
ORIGINAL ARTICLES
Studies on radon concentration in aqueous samples at Mysore city, India
BM Rajesh, MS Chandrashekara, P Nagaraja, L Paramesh
January-March 2012, 35(1):9-13
Context:
Natural radionuclides are wide spread in air, water, soil, plants and in consequence in the human diet.
222
Ra is the daughter product of
226
Ra which belongs to
238
U radioactive series.
Aims:
Radon enters the human body through ingestion of water and inhalation. Since alpha emitters are the most dangerous, studies on water containing dissolved radon are very important.
Materials and Methods:
The activity concentration of
222
Ra has been analyzed in water samples collected from lakes, open wells, drilled wells, taps and rivers in and around Mysore city, Karnataka State, India using radon emanometric technique.
Results:
The present study shows a wide range of radon concentration in water, which varies from below detection limit to 643.9 BqL
-1
with a median of 15.8 BqL
-1
. An annual effective dose with a median of 0.043 μSv y
-1
was estimated from the ingestion of
222
Ra through water.
Conclusions:
222
Rn concentration in 80% of bore-well water samples are higher than the maximum acceptable contaminant level of 11.1 BqL
-1
as prescribed by the environmental protection agency.
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4,067
557
Natural radioactivity and dose rates for soil samples around Tiruchirapalli, South India using γ-ray spectrometry
Bojarajan Senthilkumar, Sabapathy Manikandan, Mohamed Saiyad Musthafa
January-March 2012, 35(1):43-51
DOI
:10.4103/0972-0464.111409
The activity concentrations and the gamma-absorbed dose rates of the naturally occurring radionuclides
226
Ra,
232
Th, and
40
K were determined for 40 soil samples collected from Tiruchirapalli, South India, using g-ray spectrometry. The average activity concentrations of
226
Ra,
232
Th, and
40
K in the soil samples were found to be 29.9, 39.0, and 369.7 Bq kg
−1
, respectively. The measured activity concentrations of both
226
Ra and
40
K in the soil were lower than the world average, whereas, the activity of
232
Th was higher than the world average. The concentrations of these radionuclides were also compared with the average activity of the Indian soil. The radiological hazard index was calculated and compared with the internationally approved values. The average external absorbed gamma dose rate was observed to be 79.9 nGy h
−1
, with a corresponding average annual effective dose of 97.9 mSv y
−1
, which was above the world average values. The values of Ra
eq
and H
ex
were found to be within the criterion limit, whereas, the radioactivity level index (
I
g
) and total gamma dose rate were above the worldwide average values.
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333
A comparative study of
232
Th and
238
U activity estimation in soil samples by gamma spectrometry and neutron activation analysis technique
Rekha Anilkumar, S Anilkumar, K Narayani, D.A.R. Babu, DN Sharma
January-March 2012, 35(1):14-16
DOI
:10.4103/0972-0464.111404
Neutron activation analysis (NAA) is a well-established analytical technique. It has many advantages as compared to the other commonly used techniques. NAA can be performed in a variety of ways depending on the element, its activity level in the sample, interference from the sample matrix and other elements, etc., This technique is used to get high analytical sensitivity and low detection limits (ppm to ppb). The high sensitivity is due to the irradiation at high neutron flux available from the research reactors and the activity measurement is done using high resolution HPGe detectors. In this paper, the activity estimation of soil samples using neutron activation and direct gamma spectrometry methods are compared. Even though the weights of samples considered and samples preparation methods are different for these two methods, the estimated activity values are comparable.
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2,286
301
Occupational exposures in industrial application of radiation during 1999-2008
Suresh Shantaram Sanaye, Sujatha Baburajan, Suresh Ganpat Pawar, Shailesh Krishna Nalawade, Balvindar Kaur Sapra
January-March 2012, 35(1):17-21
DOI
:10.4103/0972-0464.111405
Radiation sources are used in various industrial applications like industrial radiography, industrial irradiation, industrial fluoroscopy, nucleonic gauges, well logging etc.. Gamma, beta X-ray as well as neutron sources are used for various applications. Number of radiation workers in this field has increased over the years. Due to operating conditions prevailing during the exposure as well as the strength of the sources used in some of the applications, radiation protection plays an important role in this field. Analysis of doses received by radiation workers in industry provides information on trends of doses as well as adequateness of radiation protection practices followed in this sector. In India, National Occupational Dose Registry System (NODRS) of Radiological Physics and Advisory Division (RPAD), Bhabha Atomic Research Centre (BARC) maintains personnel dose information of monitored radiation workers in the country. Analysis of occupational dose data of industrial radiation workers for last 10 years, i.e., 1999-2008 has been presented in this paper. It is observed that even though there is an increase in monitored radiation workers, percentage of persons receiving radiation exposure has come down during this period. There is also a decrease in the average annual dose as well as the collective dose. Further analysis of sub-categories shows that industrial radiography operations are the main contributor for collective dose (about 77%) followed by well logging and industrial X-ray operations (about 8% each). Thus, in addition to industrial radiography, attention is also to be given to operations in these areas.
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2,418
269
Study on the response of the ferrous ammonium sulfate - cupric sulfate dosimetry system of different salt concentrations at gamma chambers and radiation processing plant
Sayanti Ghosh, Kalpana Khedkar, Swati Kashid, Pratap Chakraborty
January-March 2012, 35(1):34-42
DOI
:10.4103/0972-0464.111408
Background and Aim:
Gamma radiation is commercially used in food preservation by extending shelf life and the success of radiation preservation of food depends upon the ability of the processor of successful measurement of the radiation dose delivered to the foods. Several dosimeters are already used in radiation processing plant to measure the delivered dose. The aim of the present study was to develop a simple and appropriate chemical dosimetry system covering a wide dose range (1-30kGy) of food irradiation.
Materials and Methods:
The response of the ferrous ammonium sulfate (Fe(NH
4
)
2
(SO
4
)
2
,6H
2
O) - cupric sulfate (CuSO
4
,5H
2
O) dosimetry system was studied at two different gamma chambers of GC-5000 and GC-900 and at a radiation processing plant with four different salt concentrations and at the dose range of 1-30kGy.
Results and Discussion:
The system with highest salt concentration i.e. with 6x0.001mmol Fe(NH
4
)
2
(SO
4
)
2
,6H
2
O + 6x0.01mmol CuSO
4
,5H
2
O showed linear response in the applied dose range of 1kGy to 30kGy. Good reproducibility of the system was observed at both GC-5000 and GC-900 with different dose rate and irradiation temperature. Routine dosimetry and dose mapping at radiation processing plant with the standard Ceric-cerous dosimetry system with same salt concentration also showed good agreement with 5% difference. The system was stable upto 7 days before and after irradiation at 4
o
C and at darkness. The estimated overall precision for the dose assessment over the dose range of interest was about 2% irrespective of the dose rate and irradiation temperature.
Conclusion:
The ferrous ammonium sulfate (Fe(NH
4
)
2
(SO
4
)
2
,6H
2
O) - cupric sulfate (CuSO
4
,5H
2
O) dosimetry system with highest salt concentration i.e. with 6x0.001mmol Fe(NH
4
)
2
(SO
4
)
2
,6H
2
O + 6x0.01mmol CuSO
4
,5H
2
O can be successfully used as chemical dosimeters in the dose range of 1-30kGy.
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SHORT COMMUNICATION
Bulk laundry monitoring system
Vaishali M Thakur, Amit Jain, Amit Verma, NR Rande, S Anilkumar, D.A.R. Babu, DN Sharma
January-March 2012, 35(1):52-54
DOI
:10.4103/0972-0464.111410
Protective wear (like boiler suits, hand gloves etc.) is necessary while handling radioactive material in plants/laboratories. During the course of work, it is quite possible that protective wear may get contaminated. These protective wear are packed in laundry bags and send to Decontamination Centre (DC) for washing. There is a need for monitoring the laundry bags at the time of receipt, as well as before dispatch to respective locations to comply with AERB guidelines. To avoid cross contamination during wash cycle, contaminated bags (>0.5 mR/h on surface) need to be segregated. Present paper describes the development of such system for monitoring surface dose rate on bags at the time of receipt.
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2,139
203
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