International Journal of Instrumentation Science

2012;  1(4): 41-44

doi: 10.5923/j.instrument.20120104.01

A different Way to Determine the Gamma-ray Linear Attenuation Coefficients of Materials

E. E. Ermis , C. Celiktas

Ege University, Faculty of Science, Physics Department, 35100, Bornova, Izmir, Turkey

Correspondence to: E. E. Ermis , Ege University, Faculty of Science, Physics Department, 35100, Bornova, Izmir, Turkey.

Email:

Copyright © 2012 Scientific & Academic Publishing. All Rights Reserved.

Abstract

In this work, gamma-ray linear attenuation coefficients of plexiglass, bakelite and Pb materials were determined to offer an alternative method for determining the gamma-ray linear attenuation coefficients of materials. Pulse shape discrimination (PSD) timing method was utilized for this purpose. 662 keV-energy photopeak radiations were used from 137Cs radioisotope. In the experiments, slow energy signals were gated from fast timing signals, coincidently. Pure photopeak signals triggered by timing signals were used in the determination of attenuation coefficients. To check the validity of the obtained experimental results, in addition, the coefficients were also calculated by Xcom code. Obtained experimental coefficients were compared with the calculated values from Xcom code and reference results.

Keywords: Gamma-ray, 137Cs, Linear Attenuation Coefficient, PSD Method, NaI(Tl) Inorganic Scintillation Detector

Cite this paper: E. E. Ermis , C. Celiktas , "A different Way to Determine the Gamma-ray Linear Attenuation Coefficients of Materials", International Journal of Instrumentation Science, Vol. 1 No. 4, 2012, pp. 41-44. doi: 10.5923/j.instrument.20120104.01.

1. Introduction

Gamma-ray linear attenuation coefficient describes the absorption of gamma-rays in unit length of an absorber material. This quantity depends on the energy of the incident gamma-ray beam and the density of the absorptive material.
Photon penetration in matter is governed statistically by the probability per unit distance travelled that a photon interacts by one physical process or another. This probability, denoted by µ, is called linear attenuation coefficient and has the dimensions of inverse length (e.g. cm-1)[1]. When an incident gamma beam with the intensity of I0 collide perpendicularly with an absorber with the thickness of x, the intensity (I) passing through the absorber can be evaluated with this equation:
(1)
Fig. 1 illustrates this equation.
NaI(Tl) (Sodium iodide activated with thallium) is one of the most commonly used inorganic scintillation detectors for gamma ray detection [2]. Inorganic crystals have great stopping power because their densities and atomic numbers are high. This feature is advantage of the inorganic crystals[3].
PSD is a kind of timing method that discriminate pulses produced by different types of incident particles to the detector surface. In this method, firstly the input signal (a) is attenuated by a significant fraction of the pulse amplitude (b). Then, the input signal is inverted and delayed (c). Finally, a bipolar timing signal is generated by adding signals which are in (b) and (c)[4]. This timing method is shown in Fig. 2.
Neutron-gamma separation[5, 6, 7, 8], background reduction and noise discrimination[9], improvement of energy resolution[10, 11] and pure particle identification[12, 13] are possible by this method.
Figure 1. Monoenergetic photons incident on a slab[4]
Figure 2. The timing method [3]
This work suggests a different spectrometer for determining gamma-ray attenuation coefficients of materials by using PSD timing technique. The gamma-ray attenuation coefficients of Pb, plexiglass and bakelite materials were investigated through this technique and the obtained experimental coefficients were compared from the results of Xcom code.

2. Experiments

Fig. 3 illustrates the schematic diagram of the used spectrometer.
Figure 3. Used setup for determining the linear attenuation coefficient. (D: Detector and photomultiplier base, PS: Power Supply, PA: Preamplifier, A: Amplifier, PSA: Pulse Shape Analyzer, TPHC: Time to Pulse Height Converter, DA: Delay Amplifier, LG: Linear Gate, C: Counter, T: Timer)
Ortec model 401A BIN, Bicron 3x3 inch NaI(Tl) inorganic scintillation detector with Ortec model 266 photomultiplier base (PMB), Ortec model 456 power supply (Bias voltage: 1000 V), Ortec model 113 preamplifiers (Input capacity: 100 pF) , Ortec model 485 amplifiers (CG: 32, FG: 6), Ortec model 427A delay amplifier (Delay: 1.25 µs), Ortec model 426 linear gate, Ortec model 776 counter, Ortec model 719 timer, Ortec model 552 pulse shape analyzer and Ortec model 437A time to pulse height converter (Range: 200 ns) were used in the spectrometer. The NaI(Tl) detector has an aluminum window of 0.5 mm to protect it from the ambient light.
The spectrometer has consisted of two branches as could be shown in Fig. 3. In the first branch, fast timing signals from the photomultiplier base of the detector (An) were sent to PSA through the preamplifier and the main amplifier. PSA and TPHC are the main parts of the PSD technique and they are used for the time derivation. PSA produces two output signals dependent on the rise time in the interval of 10-90% of the input pulse. Its outputs were then sent to the TPHC to produce a time signal. The TPHC gives an output pulse whose amplitude is proportional to time difference between its start and stop input signals.
The rise time of the analog signal produced by the detector of the photopeak radiation is different from that of the rise time of the non-photopeak radiation, discriminating of the non-photopeak radiation signal from the photopeak signal. This is the main procedure of the PSD method.
In the second branch of the spectrometer, slow energy signals from the PMB of the detector (Dy) through preamplifier, main amplifier and delay amplifier were gated with the timing signals from the first branch in the linear gate device. Thus, only photopeak radiations from the radioisotope were chosen and used in the measurements.
Most common gamma radiation source 137Cs (5 µCi) was used in the spectrometer. It was the disk shaped standard source with the diameter of 25 mm. The source was put about 4 cm away from the detector surface.
In order to test the setup, different types of absorbers as shielding materials were used. Pb, plexiglass and bakelite materials in plate shape, which plexiglass and bakelite have 10 cm x 10 cm dimensions with the thicknesses of 2 mm and Pb has same dimensions but 1 mm thickness, were chosen for determining the linear attenuation coefficients, and placed in front side of the detector. Data acquisition time was chosen as 60 s similar to the conventional attenuation setups[14, 15]. The counts from the detector were recorded versus different absorber thicknesses. These recorded counts were subtracted from the mean background value (925 counts/min.) and the semi-logarithmic absorption graphs of the absorbers were generated by using the background-free counts.
662 keV-energy photopeak position from the result of main amplifier output in energy spectrum and the TPHC output (time spectrum) were superimposed on same channel on the MCA in order to discriminate the non-photopeak radiations from the photopeak radiations.
Figure 4. The obtained time spectrum

3. Results and Discussions

The obtained time spectrum, which is the timing output of the TPHC, through the used timing method is shown in Fig. 4.
The time resolution value was found as 5.078 ns from this figure. Corresponding time per unit channel of MCA was calculated as 195 ps from this time spectrum by dividing the TPHC range to the conversion gain (1024 ch.) of the MCA.
Obtained energy spectrum (black) and the gated energy spectrum with timing signals (blue) are shown in Fig. 5. The energy resolution value was calculated as 4.22%.
Figure 5. Source spectrum (black) and the gated spectrum with timing signals (blue)
Gamma-ray attenuation graphs for the absorbers from the spectrometer were shown in Figs. 6 and 7, separately.
Figure 6. Gamma-ray attenuation graph for Pb
Figure 7. Gamma-ray attenuation graphs for plexiglass and bakelite absorbers
The slope of the absorption graph gives the experimental gamma-ray linear attenuation coefficient of the absorber material in terms of cm-1. In addition, the gamma-ray linear attenuation coefficients of the absorber materials were calculated from the mass attenuation coefficient results obtained from the Xcom code (version 3.1) developed by Berger and Hubbel[16].
In Fig. 7, the linear line was the absorption graph for bakelite and the dashed line corresponded to the absorption graph of plexiglass.
Theoretical coefficient values from the program and the experimental coefficient values for 662 keV-energy photopeak radiations of 137Cs were given in Table 1.
Table 1. Theoretical and experimental gamma-ray linear attenuation coefficients for Pb (ρ=11.35 g.cm-3), plexiglass (ρ= 1.19 g.cm-3) and bakelite (ρ= 1.25 g.cm-3) absorber materials for 662 keV energy (ρ: density)
Linear Attenuation Coefficients (cm-1)PbPlexiglassBakelite
Theoretical1.17470.09900.1018
Experimental1.1497±0.00270.0891±0.00120.0948±0.0005
Rao and Gregg[17] have reported that the linear attenuation coefficient of plexiglass is 0.1006 cm-1 for 662 keV energy. Goswami and Chaudhuri[18] have found 1.2167 cm-1 value for Pb and compared this result with the other reference values for the same energy.
From the overall comparison of the coefficients, it can be accepted that all experimental coefficient results agree with the theoretical values from the Xcom code. Due to the fact that the reference coefficient values for bakelite could not be reached, no comparison between obtained results and reference results could be performed.
Furthermore, experimental coefficients for Pb and plexiglass accord with the reference results within the estimated errors.
Due to only photopeak radiations that used in the experiments, it was believed that the experimental coefficient values normally have been found smaller than that of Xcom and reference ones.

4. Conclusions

Gamma-ray linear attenuation coefficients of Pb, plexiglass and bakelite absorber materials were investigated by using PSD timing method for 662 keV energy.
Coefficient values for the absorber materials used in the setup are agreed well with the ones obtained from the Xcom program and the reference values.
In addition to gamma attenuation coefficients via timing method, beta attenuation coefficients were obtained in Ref.[19] by using the method. It is concluded from these results that the timing technique can be used for determining both the gamma and beta-ray linear and mass attenuation coefficients of materials.
It has been shown in this work that the spectrometers for determination of gamma-ray absorption coefficients using PSD timing method might be an alternative for the conventional gamma absorption setups.

ACKNOWLEDGEMENTS

This work was supported by TUBITAK, the Scientific and Technological Research Council of TURKEY under project number 197T087 and by EBILTEM, Center of Science and Technology, Ege University under Project No. 99 BIL 001.

References

[1]  J.E. Turner, ‘Atoms, Radiation and Radiation Protection’, Wiley-VCH Verlag GmbH&Co. KGaA, Weinheim, 2007.
[2]  G.F. Knoll, ‘Radiation Detection and Measurements’, John Wiley & Sons. Inc, New York, 2000.
[3]  R.W. Leo, ‘Techniques for Nuclear and Particle Physics Experiments’, Springer–Verlag Berlin Heidelberg, Germany, 1987.
[4]  N. Tsoulfanidis, ‘Measurements and Detection Radiation’, Taylor & Francis, USA, 1995.
[5]  J. Kalyna and I.J. Taylor, ‘Pulse Shape Discrimination: An Investigation og n-γ Discrimination With Respect to Size of Liquid Scintillator’, Nucl. Instrum. and Meth., vol. 88, no. 2, pp. 277-287, 1970.
[6]  N. Zaitseva, B.L. Rubert, I. Pawelczak, A. Glenn, H.P. Martinez, L. Carman, M. Faust, N. Cherepy, S. Payne, ‘Plastic Scintillators with Efficient Neutron/Gamma Pulse Shape Discrimination’, Nucl. Instrum. and Meth., vol. 668, no. 2012, pp. 88-93, 2012.
[7]  P.A. Söderström, J. Nyberg, R. Wolters, ‘Digital Pulse Shape Discrimination of Fast Neutron and γ Rays’, Nucl. Instrum. and Meth., vol. 594, no. 2008, pp. 79-89, 2008.
[8]  T. Szczesniak, M. Moszynski, A. Syntfeld-Kazuch, L. Swiderski, D. Wolski, M. Grodzicka, G. Pausch, J. Stein, F. Kniest, M.R. Kusner, P. Schotanus, C. Hurlbut, ‘Light Pulse Shapes in Liquid Scintillators Originating from Gamma-Rays and Neutrons’, IEEE Trans. Sci. Symposium Conference Record, pp. 1480-1485, 2009.
[9]  R.C. Hochel and D.W. Hayes, ‘Background Reduction and Noise Discrimination in Proportional Counting of Tritium Using Pulse-shape Analysis’, Nucl. Instrum. and Meth., vol. 130, no. 1, pp. 183-188, 1975.
[10]  S.P. Garg, K.B.S. Murthy, R.C. Sharma, ‘Application of Pulse Shape Discrimantion Technique to ImproveThe Energy Resolution of a Gas Scintillation Proportional Counter’, Nucl. Instrum. and Meth. A, vol. 336, no. 1-2, pp. 200-205, 1993.
[11]  C. Celiktas, E.E. Ermis, M. Bayburt, ‘Energy Resolution Improvement of NaI(Tl) Scintillation Detectors by Means of a Timing Discrimination Method’, J. Radioanal. Nucl. Chem., vol. 293, no. 2012, pp. 377-382, 2012.
[12]  Gy. Mathe and B. Schlenk, ‘Pulse-shape Discrimantion Method for Particle Identification’, Nucl. Instrum. and Meth., vol. 27, no. 1, pp. 10-12, 1964.
[13]  M. Mutterer, W.H. Trzaska, Y.N. Kopatch, M. Sillanpaa, J. von Kalben, S.V. Khlebnikov, G. Schrieder, G.P. Tyruin, ‘Particle Identification with Time of Flight and Pulse-Shape Discrimination in Neutron-Transmutation-Doped Silicon Detectors’, Nucl. Instrum. and Meth., vol. 608, no. 2009, pp. 275-286, 2009.
[14]  A. Poskus, ‘Attenuation of Gamma Rays’,http://www.kkek.ff.vu.lt/uploads/erasmus/no10.pdf, accessed 16 July 2012.
[15]  ‘Interaction of Gammas’, Advanced Laboratory, University of Wisconsin Madison, Wisconsin,http://www.hep.wisc.edu/~prepost/407/gamma/gamma.pdf, accessed 16 July 2012.
[16]  M.J. Berger and J.H. Hubbell, ‘NBSIR 87-3597’, 1987.
[17]  P.S. Rao and E.C. Gregg, ‘Attenuation of Monoenergetic Gamma-rays in Tissues’, Am. J. Roentgenol, vol. 123, no. 3, pp. 631-637, 1975.
[18]  B. Goswami and N. Chaudhuri, ‘Measurements of Gamma-ray Attenuation Coefficients’, Phys. Rev. A, vol. 7, no. 6, pp. 1912-1916, 1973.
[19]  E.E. Ermis and C. Celiktas, ‘Determination of Beta Attenuation Coefficients by Means of Timing Method’, Ann. Nucl. Energy, vol. 41, no. 2012, pp. 115-118, 2012.