Measurement of Energy Resolution and Detection Efficiency of NaI(Tl) Scintillation Gamma Ray Spectrometer for Different Gamma Ray Energies
- 1Department of Physics, Haribhai V. Desai Collage, Pune-411002, Maharashtra, India
- 2Department of Physics, Haribhai V. Desai Collage, Pune-411002, Maharashtra, India
- 3Department of Physics, Haribhai V. Desai Collage, Pune-411002, Maharashtra, India
Res. J. Material Sci., Volume 4, Issue (4), Pages 7-12, May,16 (2016)
NaI (Tl) scintillation detector is widely used in experimental Physics for the measurement of induced gamma ray activity of various samples. This detector is used in the measurement of nuclear reaction Cross-section induced by neutrons and protons in activation Technique. In addition, Scintillation detector has lot of applications in the elemental analysis of various compounds, alloys using activation analysis. In each application, the precise values of detection efficiency for different gamma energies are essential. To avoid the interference of different gamma energies, knowledge of detector resolution for different gamma energies is necessary. The values of detection efficiency and resolution vary with detector size and different detector parameters. Therefore it is essential to know these values for given detector before application of detector for the quantitative analysis purpose. With this intention, in the present work, the detection efficiency and resolution of NaI(Tl) scintillation detector are measured and optimized for following gamma ray energies: 122KeV, 356KeV, 511KeV, 662KeV, 1170KeV and 1330KeV. Values of detection efficiencies for these gamma energies are found to be respectively 60.49%, 30.36%, 12.50%, 10.84%, 6.82%, and 5.89%. The values of percentage resolution for above different gamma ray energies are found to be 9.26%, 8.25%, 7.38%, 7.18, 6.32% and 5.32% respectively. The standard gamma ray sources provided by BARC are used in the present research work. The result shows that the efficiency of NaI (Tl) detector decreases with increasing gamma energy
- Body Z. and Csikai J. (1987)., Handbook on nuclear activation data IAEA, Vienna.
- Lederer C.M., Hollander J.M., Perlmanand I. and Shirley V.S. (1978)., Table of Isotope, John Wiley and sons, Inc, New York
- Dighe P.M., Pansare G.R., Ranjita sarkar and Bhoraskar V.N. (1991)., Cross section of (n,2n) reactions induced by 14.7 MeV neutrons in Ti-46,Cr-50 and Co-59, Indian journal of pure and applied Physics, 29, 665-667.
- Pansare G.R., Dighe P.M. and Bhoraskar V.N. (1992)., Estimation of Zirconium in Fe and Ti Based Alloys Through formation of Zr-90m At 14.7 MeV Neutrons, Radiat. Phys. Chem. 40(3), 213-216.
- Dighe P.M., Pansare G.R., Kulkarni S.G. and Bhoraskar V.N. (1992)., Use of 14 MeV Neutrons in analysis of explosive Class materials, Journal of radio analytical and nuclear chemistry, articles, 162(2), 277-282, Hungary.
- Pansare G.R., Nagesh N. and Bhoraskar V.N. (1994)., A study on grafting of acrylonitrile onto high density polyethylene by the neutron activation., J. Phys. D: appl. Phys 27, 871-874.
- Muraleedhara Varier K., Joseph A. and Pradyumnan P.P. (2015)., Advanced Experimental Techniques in Modern Physics, Calicut, India