Detection Efficiency of NaI(Tl) Detector in 511-1332 keV Energy Range

Abstract

As it is important to obtain accurate analytical result in an experimental research, this required quality control of the experimental system. Gamma spectrometry system can be used in a variety of different fields such as radiation and medical physics. In this paper the absolute efficiency, peak to valley ratio, and energy resolution of a [superscript] 3 [variant prime] [variant prime] [/superscript] × [superscript] 3 [variant prime] [variant prime] [/superscript] NaI(Tl) detector were determined experimentally for 511, 662, 835, 1173, 1275, and 1332 keV photon energies obtained from 22Na, 54Mn, 60Co, and 137Cs radioactive sources.

I. Akkurt 1 and K. Gunoglu 2 and S. S. Arda 1

Academic Editor:Jakrapong Kaewkhao

1, Fen-Edebiyat Fakultesi Fizik Bol, Suleyman Demirel University, 32260 Isparta, Turkey
2, Teknsk Bil. MYO, Suleyman Demirel University, 32260 Isparta, Turkey

Received 13 August 2013; Revised 9 December 2013; Accepted 15 December 2013; 12 March 2014

This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

1. Introduction

With the start of using radioactive sources in a variety of different fields such as health physics, industry, energy, and environmental application nuclear radiation detectors become the most fundamental instruments as radiation is hazardous for health. In a radiation measurement an accurate knowledge of the detector spectral performance is required. As the radiation can travel large distances between the interactions in the detector material before detection is possible, the detectors do not have 100% efficiency. In the radiation measurement, one of the most important characteristics of a detector is the efficiency of the detector. Gamma spectrometry is one of the most widely used detector systems in this field and its performance directly depends on the knowledge of the detection efficiency. The detection efficiency is a measure of the percentage of radiation that a given detector detects from the overall yield emitted from the source. It can vary with the volume and shape of the detector material, absorption cross-section in the material, attenuation layers in front of the detector, and distance and position from the source to the detector [1].

Detection efficiency of a detector system depends on different parameters and thus various kinds of the efficiency definitions are used to cover those parameters.

(i) Absolute efficiency: it is the ratio of the number of counts recorded by the detector to the number of gamma rays emitted by the source (in all directions).

(ii) Intrinsic efficiency: it is the ratio of the number of pulses recorded by the detector to the number of gamma rays hitting the detector.

(iii): Full-energy peak (or photopeak) efficiency: it is the efficiency for producing full-energy peak pulses only, rather than a pulse of any size, for the gamma ray.

Especially in the radioactivity measurement the absolute efficiency of the detector must be known. It is defined as the ratio of the number of counts recorded by the detector ( _{N c} ) to the number of radiation ( _{N s} ) emitted by the source (in all directions) as represented in the following formula: [figure omitted; refer to PDF] Absolute efficiency of the detector depends not only on detector properties but also on the details of the counting geometry.

Various experimental and calculation works have been reported for the detection efficiency work [2-6].

For the gamma ray spectrometry, the absolute efficiency and energy resolution are important parameters to be determined. Those parameters are usually done using a function to fit the efficiency at a wide energies range, as the number of energy peaks obtained from radioactive sources is limited. For these purposes the absolute efficiency and the energy resolution of the NaI(Tl) detector have been determined experimentally at 511, 662, 835, 1173, 1275, and 1332 keV energies obtained from ²² Na, ⁵⁴ Mn, ⁶⁰ Co, and ¹³⁷ Cs radioactive isotopes.

2. Experimental Methods

The gamma ray spectrometry consists of a 3 × ^{3 [variant prime] [variant prime]} NaI(Tl) detector and this is connected to 16384-channel Multichannel Analyser (MCA). The spectrum obtained from MCA is analyzed using the Genie 2 software obtained from Canberra [7-9]. In order to reduce the background level of the system, the detector is shielded using 6 cm lead on all sides. A schematic view of the system has been displayed in Figure 1. The 4 different radiation sources (²² Na, ⁵⁴ Mn, ⁶⁰ Co, and ¹³⁷ Cs) that give 511, 662, 835, 1173, 1275, and 1332 keV gamma ray energy were placed at 5 different distances (0,5, 1, 3, 5, and 10 cm) from the face of detector and the measurement has been performed for each source. Each measurement has been done for a period of 60 min to obtain good statistics in the evaluation of each gamma peak. Typical gamma ray spectrum for ¹³⁷ Cs and ⁶⁰ Co sources taken with the NaI(Tl) detector is given in Figures 2 and 3. In Table 1 the present activity and half-life of the radioisotope sources are given and in Table 2 the energies and emission probabilities of the radioisotope source are given.

Table 1: The present activity and half-life of the radioactive sources used to obtain energies.

Nuclide	Activity (micro Ci)	Half-life (day)
22 Na	0.706	950.8
54 Mn	0.348	312.3
137 Cs	0.970	11020.0
60 Co	0.843	1925.5

Table 2: The energies and emission probabilities of the radioisotope source [11].

Nuclide	Energy (keV)	Emission probability (%)
22 Na	511.00	178.00
1274.60	99.94
54 Mn	834.83	85.59
137 Cs	661.66	85.30
60 Co	1173.23	99.85
1332.48	99.98

Figure 1: Schematic view of the experimental system.

[figure omitted; refer to PDF]

Figure 2: Gamma ray spectrum obtained from ¹³⁷ Cs source.

[figure omitted; refer to PDF]

Figure 3: Gamma ray spectrum obtained from ⁶⁰ Co source.

[figure omitted; refer to PDF]

3. Results and Discussions

The properties such as detector efficiency, energy calibration, and energy resolution of a NaI(Tl) detector have been measured for 6 different gamma ray energies.

3.1. Efficiency Calibrations

The detection efficiency of the NaI(Tl) detector was obtained using (1) for each gamma ray energy emitted by the ²² Na, ⁵⁴ Mn, ⁶⁰ Co, and ¹³⁷ Cs radioactive isotopes. The obtained results have been displayed as a function of gamma ray energy in Figure 4. As can be seen from this figure, there is a great variety of analytical functions that is used to describe the efficiency dependence on the energy. The solid line represents a second degree polynomial fit that gives a good description with the correlation coefficient between the efficiency values and the gamma ray energies, which is about ^{R 2} = 0,94.

Figure 4: Detection efficiency of NaI(Tl) detector as a function of gamma ray energies (source placed at 0,5 cm distance to the detector face).

[figure omitted; refer to PDF]

As the detection efficiency of the NaI(Tl) detector can vary with the distance to the detector face, the efficiencies have been obtained for 5 different distances from the detector. The results are displayed in Figure 5 for 5 different distances and 6 different energies. It can be seen from this figure that the detection efficiency has decreased exponentially with the increasing distance from detector face.

Figure 5: Variation of detection efficiency of NaI(Tl) detector as a function of distance.

[figure omitted; refer to PDF]

The obtained results have been compared with the calculation obtained using the same detector size [10]. The comparisons have been displayed in Figures 6 and 7 where 0.5 and 10 cm distances have been used. A good agreement between experimental and calculated results was obtained as can be seen from these figures.

Figure 6: Comparison of measured and calculated detection efficiency of NaI(Tl) detector (source placed at 0,5 cm distance to the detector face).

[figure omitted; refer to PDF]

Figure 7: Comparison of measured and calculated detection efficiency of NaI(Tl) detector (source placed at 10 cm distance to the detector face).

[figure omitted; refer to PDF]

3.2. Energy Calibrations and Resolution

The detector system should be calibrated before using in radiation detection in order to covert channel number to energy scale. This is carried out under laboratory conditions that mimic as closely as possible the experimental conditions. Several radioactive sources (at least 3 different energy peaks) are used to get certain peak to see channel number. This is usually done using ¹³⁷ Cs and ⁶⁰ Co radioactive sources as they produce γ -ray energy of 662, 1170, and 1332 keV, respectively. In Figure 8 the γ -ray spectrum obtained from those sources and related fit has been displayed.

Figure 8: Energy spectrum and calibration fit for ¹³⁷ Cs and ⁶⁰ Co sources.

[figure omitted; refer to PDF]

The energy resolution of a detector system is obtained from the peak full width at one-half of the maximum height (FWHM) of a single peak using the following equation: [figure omitted; refer to PDF] Here R is energy resolution and _{E o} is the related energy. It will provide the separation for two adjacent energy peaks which will lead to identification of different nuclide in spectrum. The measured energy resolution of the NaI(Tl) detector is displayed in Figure 9 as a function of gamma ray energy. It can be seen from this figure that the energy resolution of the NaI(Tl) detector decreased with the FWHM with the increasing gamma ray energy.

Figure 9: Energy resolution of the NaI(Tl) detector obtained for 0,5 cm distance.

[figure omitted; refer to PDF]

4. Conclusions

The detection efficiency and energy resolution for the NaI(Tl) scintillation detectors were measured. The variation of detection efficiency with the gamma ray energy and detection distance was also investigated. It was found from this work that the detection efficiency depends on gamma ray energy and also source distance to the detector.

Acknowledgments

This work has been supported partly by the Suleyman Demirel University Foundation Unit (3312-YL2-12) and partly by the State Planning Unit (DPT2006K-120470) in Turkey.

Conflict of Interests

The authors declare that there is no conflict of interests regarding the publication of this paper.

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