Home About us Editorial board Search Ahead of print Current issue Archives Submit article Instructions Subscribe Contacts Reader Login
Home Print this page Email this page Small font size Default font size Increase font size Users Online: 132
Export selected to
Reference Manager
Medlars Format
RefWorks Format
BibTex Format
  Access statistics : Table of Contents
   2016| July-September  | Volume 39 | Issue 3  
    Online since November 30, 2016

  Archives   Previous Issue   Next Issue   Most popular articles   Most cited articles
Hide all abstracts  Show selected abstracts  Export selected to
  Viewed PDF Cited
Beta response of CaSO4:Dy based thermoluminescent dosimeter badge and its angular dependence studies for personnel monitoring applications
Munish Kumar, RB Rakesh, C Sneha, P Ratna, AK Bakshi, D Datta
July-September 2016, 39(3):132-137
Studies on the response of 0.4 mm and 0.8 mm thick Teflon embedded CaSO4:Dy discs are carried out using different beta sources having energy ranging from 0.224 to 3.54 MeV. Angular dependence of the response for 0.4 and 0.8 mm thick thermoluminescence (TL) discs was also studied for 85 Kr and 90 Sr/90 Y beta sources. The ratio of the response of the open disc to that under 1.5 mm thick Perspex filter (DOpen/DPerspex) was estimated for 0.4 and 0.8 mm thick TL discs in the energy range from 0.689 to 3.54 MeV. The evaluation of (DOpen/DPerspex) ratio is necessary as same is used to estimate the energy of beta particles and to apply appropriate correction factor while evaluating beta dose. In addition to above, the optical density and transmission characteristics for 0.4 and 0.8 mm thick Teflon and CaSO4:Dy Teflon embedded discs are also reported.
  1,947 242 4
Determination of uranium concentrations and 234U/238U activity ratio in some granitic rock samples by alpha spectrometry: Application of a radiochemical procedure
Mahmoud R Khattab
July-September 2016, 39(3):122-127
The present study is an application of a radiochemical procedure using alpha spectrometry technique for determination of uranium isotopes 238 U,234 U, and 235 U on 13 granitic samples. These samples were collected from Gabal Gattar area, Northeastern Desert, Egypt. The collected samples were digested using microwave technique with aqua regia and spiked with 232 U for chemical yield and activity calculation. Separation of uranium isotopes from the samples was done by Dowex 1 × 4 (50–100 mesh) resin followed by source preparation using microprecipitation technique. The concentrations of 238 U were ranged between 28.9 ± 0.9 and 134.8 ± 1.8 Bq/g, and the 234 U concentrations were between 24 ± 0.6 and 147.7 ± 2.2 Bq/g. For the 235 U, the activity concentrations were between 1.3 ± 0.2 and 6.7 ± 1.2 Bq/g. The activity ratio of 234 U/238 U was calculated and varied from 0.80 to 1.30.
  1,654 318 1
Study on urea breath test a tool for Helicobacter pylori infection
RV Kolekar, Anita Gadgil, S. P. D. Bhade, Priyanka Reddy, Prashant Bhandarkar, N Roy, SP Patil, Rajvir Singh
July-September 2016, 39(3):146-148
Urea breath test (UBT) is commonly used diagnostic test for detecting the presence of Helicobacter pylori bacteria in the stomach. The patient undergoing the UBT ingests one microcurie of urea capsule containing labeled carbon-14. After ingestion of the capsule, the patient blows into a trapping solution. H. pylori bacteria in the stomach releases enzyme urease which breaks urea capsule to release carbon dioxide tagged with carbon-14 in the exhaled breath. Carbon-14 in the trapping solution is counted in liquid scintillation counter. In this study, 261 patients suspected of H. pylori infection had undergone UBT. It was found that 52% of the patients tested positive for H. pylori infection. No significant difference observed between various age groups. There was no statistically significant difference between the infection rates in males and females.
  1,567 160 -
What can we tell people about the health effects of radiation exposure?
Anthony D Wrixon
July-September 2016, 39(3):117-121
  1,049 223 -
Validation of intensity-modulated radiotherapy commissioning as per recommendations in test plans of the American Association of Physicists in Medicine task group 119 report
Sandeep Kaushik, Atul Tyagi, Lalit Kumar, Man Pal Singh, Rajender Singh Kundu, Rajesh Punia
July-September 2016, 39(3):138-145
In the present study, intensity-modulated radiotherapy (IMRT) commissioning has been validated as per the task group report 119 (TG119) of the American Association of Physicists in Medicine (AAPM). The plans have been done on structure and computed tomography scanned data set downloaded from the AAPM website. IMRT test planning has been performed to achieve conformed dose and dose distribution similar to that described in the AAPM TG119 report. Point dose measurements with ionization chamber have been taken on solid water phantom at a depth of 7.5 cm. Measurements were performed in two locations, i.e. at target volume and low dose avoidance structure, with planned machine parameters. Gamma evaluation of dose distribution produced by each field has also been done individually using electronic portal imaging device (EPID). Overall mean deviation obtained for ion chamber measurement was −0.012 (standard deviation [SD]: 0.015) with confidence limit (CL) 0.043 and −0.0012 (SD: 0.009) with CL 0.020 in high-dose region and low-dose region, respectively. Overall mean gamma passing in portal dosimetry calculated specifically for EPID has been observed 99.5% with SD 0.33 and CL 1.13. The results obtained for ion chamber dosimetry and portal dosimetry are much better than those reported in the AAPM TG119 report. Better results in gamma evaluation further reduced CL for EPID users.
  925 170 -
Development of methodology for validation of efficiency of 85Kr monitoring system by portable HPGe spectrometer
J. P. N. Pandey, Pankaj Kumar, Ganesh Bhagwan Talole, Anish Ahmed Ansari, Vikas Kumar Gupta, G Ganesh, RM Tripathi
July-September 2016, 39(3):128-131
85Kr a fission product noble gas is released into environment through stack at reprocessing plants during dissolution of spent fuel. Dual GM tube based online monitoring system having efficiency 0.5% for 85Kr is used for quantification of 85 Kr activity released through stack. Efficiency calibration of online monitoring system requires use of standard 85Kr source which is not readily available. As per safety regulations periodic efficiency calibration of Krypton monitoring system is required to be done at least once a year. This paper presents an indigenously developed methodology for efficiency validation of krypton monitoring system using portable HPGe gamma spectrometer.
  818 165 1
Impact assessment of naturally occurring radioactive materials on the public from gold mining and processing at Newmont Golden Ridge Limited, Akyem, Eastern Region of Ghana
Augustine Faanu, Oscar Kwaku Adukpo, Charles Kansaana, Lordford Tettey-Larbi, Henry Lawluvi, David Okoh Kpeglo, Emmanuel Ofori Darko, Geoffrey Emi-Reynolds, Razak Abdul Awudu, Peter Atta Amoah, Alex Opoku Efa, Ali Doe Ibrahim, Benice Agyeman, Rita Kpodzro, Lilian Agyeman
July-September 2016, 39(3):155-164
Baseline radioactivity levels of naturally occurring radioactive materials within the operational area and surrounding communities of Akyem Gold Mine of Newmont Golden Ridge Limited of Ghana were determined based on direct gamma-ray spectrometry to quantify the radionuclides of interest, namely,238 U,232 Th, and 40 K in soil samples. The average activity concentrations of 238 U,232 Th, and 40 K in the soil samples were 11.90, 11.39, and 139.71 Bq/kg, respectively. For the water samples, the concentration values of gross-alpha and gross-beta for all the water samples were below the Ghana Standards Board (now Ghana Standards Authority) and World Health Organization recommended guideline values for drinking water quality. The annual average effective dose to the public due to gamma ray exposures from the soil samples was estimated to be 0.03 mSv which is below the UNSCEAR 2000 average reference level of 0.07 mSv for public exposure control. The results obtained in this study also show that radiation levels are within the natural background radiation levels found in literature and compare well with the results of similar studies in Ghana.
  647 113 1
Methodology for estimation of phosphorus-32 in bioassay samples by Cerenkov counting
Sonal M Wankhede, Pramilla D Sawant, Rakesh Kumar B Yadav, DD Rao
July-September 2016, 39(3):149-154
Bioassay is the preferred individual monitoring technique for radiation workers handling phosphorus-32 (32 P), a pure beta emitter (βmax = 1.71 MeV) with 14.3 day half-life. The method standardized at Bioassay Laboratory, Trombay and in use for this purpose includes estimation of 32 P in urine by coprecipitation with ammonium phosphomolybdate followed by gross beta counting. In this study, the feasibility of Cerenkov counting for detection of 32 P in bioassay samples was explored, and the results obtained were compared with the conventional gross beta technique.
  596 122 1
Health physics operating experience in transporting cleanup spent resin and verification of methodology for estimating the shielding thickness of cask
Bahadur Singh K Rautela, Sarat R Sahu, PS Raveendran, Prakash K Kothare, Sudip Ranjan Mitra, B. S. V. Ramana Murthy
July-September 2016, 39(3):165-169
Cleanup (CU) demineralizer of TAPS 1 and 2, containing mixed bed resins, is used to maintain reactor water chemistry. Once the bed is saturated, spent resin needs to be transferred to resin fixation facility for fixation and subsequent disposal in near-surface disposal facility. This is done by transporting the spent resin in a shielded resin transportation cask (SRTC) from radwaste building. The SRTC was manufactured with shielding thickness, based on methodology proposed by Rautela et al., “Shielding adequacy of proposed cask for transporting TAPS 1 and 2 CU spent resins.” Extensive radiation monitoring was carried out during the entire transfer and transportation process. Observed radiation levels on cask surface were within the accepted and calculated radiation levels. This paper describes verification methodology proposed by Rautela et al. and health physics operating experience during first CU spent resin transfer process at TAPS 1 and 2.
  522 102 -
Summary of a report, “nuclear power and the clean energy future”
DD Rao
July-September 2016, 39(3):170-171
  474 118 -