Scholarly article on topic ' The standardization methods of radioactive sources ( 125 I, 131 I, 99m Tc, and 18 F) for calibrating nuclear medicine equipment in Indonesia '

The standardization methods of radioactive sources ( 125 I, 131 I, 99m Tc, and 18 F) for calibrating nuclear medicine equipment in Indonesia Academic research paper on "Earth and related environmental sciences"

CC BY
0
0
Share paper
Academic journal
J. Phys.: Conf. Ser.
Keywords
{""}

Academic research paper on topic " The standardization methods of radioactive sources ( 125 I, 131 I, 99m Tc, and 18 F) for calibrating nuclear medicine equipment in Indonesia "

lopscience

¡opscience.iop.org

Home Search Collections Journals About Contact us My IOPscience

125 131 99m 18

The standardization methods of radioactive sources ( I, I, Tc, and F) for calibrating nuclear medicine equipment in Indonesia

This content has been downloaded from IOPscience. Please scroll down to see the full text. View the table of contents for this issue, or go to the journal homepage for more

Download details:

IP Address: 107.190.129.162

This content was downloaded on 25/06/2016 at 03:23

Please note that terms and conditions apply.

Journal of Physics: Conference Series 694 (2016) 012060

The standardization methods of radioactive sources (125I, 131I, 99mTc, and 18F) for calibrating nuclear medicine equipment in Indonesia

G Wurdiyanto1 and H Candra1

1 Center for Technology of Radiation Safety and Metrology (PTKMR)

National Nuclear Energy Agency of Indonesia (BATAN)

Jalan Lebak Bulus Raya, No. 49, Jakarta Selatan, Indonesia 12440

E-mail: gatot_w@batan.go.id

Abstract. The standardization of radioactive sources (125I, 131I, 99mTc and 18F) to calibrate the nuclear medicine equipment had been carried out in PTKMR-BATAN. This is necessary because the radioactive sources used in the field of nuclear medicine has a very short half-life in other that to obtain a quality measurement results require special treatment. Besides that, the use of nuclear medicine techniques in Indonesia develop rapidly. All the radioactive sources were prepared by gravimetric methods. Standardization of 125I has been carried out by photonphoton coincidence methods, while the others have been carried out by gamma spectrometry methods. The standar sources are used to calibrate a Capintec CRC-7BT radionuclide calibrator. The results shows that calibration factor for Capintec CRC-7BT dose calibrator is 1,03; 1,02; 1,06; and 1,04 for 125I, 131I, 99mTc and 18F respectively, by about 5 to 6 % of the expanded uncertainties.

1. Introduction

The utilization of nuclear technology in all fields has grown rapidly both in the international as well as in Indonesia. In their application, it is required the standard sources that meets the technical requirements so that their products have a sufficient level of quality. Some laboratories use standard to calibrate owned measuring apparatus, as well as the guarantor of quality for their products. One of the requirements that are used to obtain a qualified standard reference material will require an adequate level of homogeneity. Based on the duties and functions as a laboratory of national reference in the field of the measurement of radioactivity, then Center for Technology of Radiation Safety and Metrology (PTKMR-BATAN) must be able of provide a liquid standard source with various types that qualify as standard reference materials so that results of the measurement and testing of samples has a value of accurate, precise and traceable to the International System.

To solve that problems, it is required some procedures to calibrate the radionuclide calibrators that are used by hospitals for routine measurement of activity of 125I, 131I, 99mTc and 18F that was administered to patients. Although 137Cs is used to monitor the radionuclide calibrator, standards of 125I, 131I, 99mTc and 18F are required to determine the calibration factors for this radionuclide.

Iodine-125 has a half-life of 59.388 (28) days, decay by electron capture and emits X-ray photon at 27 keV (112.5%), 31 keV (20.9%), 32 keV (4.5%), as well as y-rays at 35.5 keV (6.6%) and Auger and conversion electrons between 22 and 35 keV (Chiste and Be, 2011). Iodine-131 has a half-life of 8.0233 (19) days, disintegrates through emission to the excited levels of 131Xe, the isomeric state 131mXe included, and y-ray at 364.46 keV (82.6%), 636.97 keV (7.12%), and 722.89 keV (1.78 %),

0 I Content from this work may be used under the terms of the Creative Commons Attribution 3.0 licence. Any further distribution

I of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI. Published under licence by IOP Publishing Ltd 1

Journal of Physics: Conference Series 694 (2016) 012060

(Chiste and Be, 2004). Technicum-99m decays with a half-life 6.0067(10) hours, mainly by isomeric transition to 99Tc. The most intense gamma transitions are 2.1726 keV (99.0%) and 140.511 keV (99.0%) (Chiste and Be, 2004). Fluorine-18 disintegrates to the ground state of 18O by positron emission with an intensity of 96.86(19) % and electron capture with an intensity of 3.14(19)%. The half-life of 18F is 1.8288 (3) hours. The positron has a maximum energy of 633.5 keV and an average energy of 249.3 keV. The 511 keV annihilation radiation following the positron emission has an intensity of 193.72 %. The decay data are those given by the International Bureau of Weights and Measures, or BIPM (BIPM, 2004).

This paper describes the procedures used to standardize the activity of 125I, 131I, 99mTc and 18F, and the results of the measurements used to calibrate the nuclear medicine equipments in Indonesia. The volume of 18F solutions used was about 16 ml because this is the volume most often used in hospitals. Vials that are used are made by Wheaton, USA and are made of borosilicate glass, with a volume of 20 ml, height of 55 mm, outer diameter of 30 mm, and thickness of 1 mm.

The PTKMR-BATAN Secondary Standard Ionization Chamber is a Capintec CRC-7BT radionuclide calibrator that is used as a working chamber for the routine dissemination of activity standards for photon emitting radionuclides. The calibrator is checked routinely to ensure constancy and relative accuracy using standard sources from national metrology institutes (NMIs). This apparatus is calibrated using standard sources that are calibrated by the gamma-ray spectrometry method for 131I, 99mTc and 18F radionuclides, but for 125I is measured by absolute photon-photon coincidence counting methods. The activity concentrations of radioactive solutions are calibrated in the point source geometry first, and then standard sources are prepared in other geometries by careful gravimetric transfer of the calibrated solution into ampoules or vials.

2. Methodology

2.1. Preparation of sources

Source solutions of 125I and 131I in the form of potassium iodide (KI) in H2O was diluted by a factor of 10.25 for 125I and 6.53 for 131I. From that solution, point sources were prepared by droping about 10 -25 mg onto a thin polyethilene plastic backing. After dispensing the droplet of 125I and 131I onto the source support, a drop of AgNO3 solution was added immediately to precipitate the volatile iodium anion (I-) as AgI. In addition, the reminder of the original source and the dilution source solution of 125I were transferred into five PTKMR type glass ampoules. The masses of all samples, about 2 g, were determined gravimetrically using KERN ABT 220-5DM type balance, traceable to SI through the Calibration Laboratory of Indonesia.

99mTc solution is obtained from molydenum generator was prepared in the form of ampoules and thin film layer of mylar. Preparation was carried out by gravimetric method using a calibrated semimicro balance device because it is more accurate than other methods. 5 pieces of point sources and 3 ampoules were prepared. All of the point sources were dripped on mylar buffer and then dried using infra-red lamp. The dried sources were covered with a mylar layer and coded and ready to be measured.

18F is obtained through the reaction 18O(p, n)18F using a cyclotron that is situated in a hospital in Jakarta. The chemical form of 18F that is used is FDG (fluoro-deoxyglucose) without carrier solution. Three sets of measurements were made and, for each, between 3 and 5 point sources were prepared together with a single 16 ml liquid source in a vial. The 18F point source and the solution in the vial originated from the same master solution.

The point sources had a sample diameter of about 4 mm, and the weight varied between 10 and 15 mg. After drying under a heat lamp for about 30 minutes, they were then covered with a film of mylar with a ± 25 ^g/cm2 thickness. The samples was measured in the activity range of 103 Bq to 4.0 105 Bq. Preparation of the vials is done by gravimetric transfer of a volume of about 16 ml. The density of the solution was measured as 1.033 g/ml.

Journal of Physics: Conference Series 694 (2016) 012060

2.2. Activity measurement

2.2.1. Photon-photon gamma coincidence measurements. All of the 125I point sources were measured absolutely by a photon-photon coincidence system that was constructed in PTKMR-BATAN. The system using two NaI(Tl) detectors, crystal size of 76 mm diameter x 6 mm thickness with 0.5 mm aluminium window, connected to coincidence unit. The measurements were carried out twice with 25 replicates. Their activity was measured using source to detector distances ranging from 2 to 100 mm, to obtain varying detection efficiencies. Measurements were taken in the energy region between 13 and 100 keV. The duration for individual measurements varied between 100 s at low distance and 500 s at larger distances. Three counting rates were corrected for background, dead time and resolving time for the coincidence count rate. The activity of 125I was calculated using the equation for photon photon coincidence counting by Schrader and Walz (1987) and Schrader (1990, 2006).

2.2.2. y-spectrometry measurements. The activities of all of the point sources were measured by gamma spectrometry. The detector is an HPGe model GC1018 (Canberra, USA), which has a relative efficiency of 10.3% with an energy resolution of 1.69 keV FWHM at 1332.5 keV. The detector is equipped with a model 2002CSL pre-amplifier, and a Canberra model 2020 amplifier and operates at a bias voltage of +4500 V. Signals from the detector are processed by the Canberra gamma spectrum analysis system using GENIE 2000 software (Canberra Industries, USA). The source-to-detector distance was 25 cm. As described above, the gamma-ray spectrometry system was first calibrated using standard sources of 152Eu, 60Co and 137Cs that have traceability to the SI. Three sets of measurements were made with a counting time of 10 minutes in each case. Impurities were also checked using gamma spectrometry.

2.2.3. Measurement with ionization chamber. All of the liquid solutions in ampoule or vial glass were measured using the Capintec radionuclide calibrator ionization chamber in two ways, firstly with the predefined calibration factor corresponding to the each (125I, 131I, 99mTc and 18F) button on the activity calibrator and secondly using the dial setting determination method. Preset push-buttons are provided for quick selection of the calibration number of the most often used radioisotopes. Thus, the calibration settings for each radionuclide and geometry should be determined individually.

The determination of the appropriate dial settings in this work was achieved in the manner described by Zimmerman and Cessna (2000). The ratio, R, of the activity measured with the special button on the standard activity, is determined after the gamma spectrometry activity results are known. The ratio R is given by R = Astd / Acap, where Astd is the activity of standard source and Acap is the activity measured by the Capintec radionuclide calibrator. This R value can be used directly as a calibration factor for the 18F and 99mTc when the special button or calibration setting number is used.

3. Results and discussion

The efficiency (81,82) of the detector varied between 0.12 to 0.05. This values is determined by variation of the detector to source distance between 2 mm to 100 mm. The absolute activities of 125I source could be obtained from a plot of the activity distribution versus x = f(81, 82), as shown in figure 1. The relative standard deviation (counting statistics) of the measurement result for individual sources varied from 0.4% to 0.5%. The average activity concentration of the 125I solution derived from photon-photon coincidence measurement results was (441.7 ± 4.0) kBq g-1. The relative standard uncertainty components are presented in table 1.

The result of the efficiency calibration for the HPGe detector using 152Eu, 60Co and 137Cs standard sources is shown in figure 2. The energies used to produce the efficiency calibration curve were 244.7, 344.3, 661.657, 778.9, 964.1, 1112.1, 1173.228, 1332,492 and 1408.0 keV, resulting in a curve described by the equation efficiency at energy E = 0.1598 e-0.98 with a correlation coefficient of 0.9998. The uncertainty of the interpolated efficiency at any point is 1.5 % at k = 1. This value was

13th South-East Asian Congress of Medical Physics 2015 (SEACOMP) IOP Publishing

Journal of Physics: Conference Series 694 (2016) 012060 doi:10.1088/1742-6596/694/1/012060

determined from the residuals between the true efficiencies and the efficiencies obtained from the efficiency curve.

There was no significant impurity detected above 0.05% of the 125I, 131I, 99mTc and 18F activity. This value was determined when the Capintec radionuclide calibrator was calibrated. The counting time was 10 minutes, and the time difference between the gamma spectrometry and Capintec radionuclide calibrator measurements was about 8 half-lives of 131I, 99mTc and 18F, respectively. The results of the activity determinations of the 125I, 131I, 99mTc and 18F solution are shown in table 2. The corrections on standardization of radioactive sources are impurity, dead time, background counts, half-life, and decay on process of counting.

Figure 1. An example of activity distribution versus x = f(s1,s2).

Tabel 1. Relative uncertainty components of the 125I activity concentrations (in %).

Components U,(%) Type

Statistics counting 0.54 A

Counting time 0.035 B

Weighing 0.2 B

Dead time 0.05 B

Background 0.35 B

Resolving time 0.1 B

Decay parameters 0.13 B

Impurity 0 -

Extrapolation 0.5 B

Combined Uncertainty (k=1) 0.86

Tabel 2. The result of activity measurement base on gamma spectrometry and photon-photon coincidence system.

Nuclide Activity Methods Dose Calibration

(MBq) calibrator Factor

_(MBq)_

125I 7.30 coincidence 7.11 1.03

131I 109.23 spectrometry 107.22 1.02

99mTc 214.67 spectrometry 201.67 1.06

18F 744.82 spectrometry 715.23_1.04

Table 3, shows some types of components used to determine the value of the measurement an expanded uncertainty that used the gamma spectrometer equipment, dose calibrator and the coincidence system. Several components have the same uncertainty value, this is because the standard sources used are the same, namely 152Eu, 137Cs, and 60Co. The experimental results showed that if the

Journal of Physics: Conference Series 694 (2016) 012060

specific button is used for about 16 ml solutions, the correction factor, R, would be 1.03, 1.02, 1.06, and 1.04 for 125I, 131I, 99mTc and 18F, respectively; with an expanded uncertainty of 4.9, 5.7, 5.6, and 5.7 % with 95 % of confidence level at coverage factor, k=2. 125I has an expanded uncertainty smallest because it used absolute methods for standardizing that nuclide.

Figure 2. Efficiency calibration curve using 152Eu, 60Co and 137Cs standard sources.

Table 3. Uncertainty components for the R-value determined by gamma-ray spectrometer and dose calibrator for 125I, 131I, 99mTc, and 18F.

Standard uncertainty components (%)

Source of uncertainty 125j 131I 99mTc 18p Type

Gamma-ray Spectrometer:

Standard Source - 0.5 0.5 0.5 B

Half- life of standard - 0.12 0.12 0.12 B

Efficiency - 1.5 1.5 1.5 B

Intensity of sample - 0.6158 0.2695 0.1962 B

Half life of sample - 0.0237 0.0166 0.0164 B

Area of sample - 0.56 0.56 0.67 A

Dead time - 0.05 0.05 0.05 B

Photon-photon coincidence 0.86 - - - Comb.

Ionization chamber :

Half-life of sample 0.0471 0.0237 0.0166 0.0164 B

Statistics of counting 0.60 0.50 0.48 0.6 A

Detector response 1.155 1.155 1.155 1.155 B

Accuracy of reading 1.732 1.732 1.732 1.732 B

Repeatability 0.577 0.577 0.577 0.577 B

Non-linearity 0.35 0.35 0.35 0.35 B

Mass 0.05 0.05 0.05 0.05 B

Combined standard uncertainty 2.45 2.87 2.82 2.86

Expanded Uncertainty (k = 2) 4.9 5.7 5.6 5.7

4. Conclusion

Standardization of radioactive sources 125I, 131I, 99mTc, and 18F have been successfully carried out in PTKMR - BATAN. The use of standard sources that has been standardized by PTKMR can well be used to calibrate the dose calibrator Capintec CRC 7 BT. Calibration factor values of dose calibrator are 1,03; 1,02; 1,06; 1,04 respectively for the source of 125I, 131I, 99mTc and 18F, with the value of the expanded uncertainty of a stretch of 4.9, 5.7, 5.6, and 5,7 for a confidence level of 95 % at coverage factor, k = 2. PTKMR-BATAN can calibrate the equipment in field of nuclear medicine using a short half-life of 125I, 131I, 99mTc and 18F standard source.

References

[1] BIPM 2004 Table of Radionuclides Monographie BIPM-5. Bureau International des Poids et Mesures, Pavillon de Breteuil Sevres

Journal of Physics: Conference Series 694 (2016) 012060

[2] Chiste V and Be M M 2011 125I. Table of Radionuclides (Vol. 6-A = 22-242), Monographie

BIPM-5, BIPM, Sevres, pp. 37-41.

[3] Schrader H 1990 Standardization of 129I by tracer method with photon-photon coincidences

from decay of 125I Appl. Radiat. Isot. 41(4) 417 - 421

[4] Schrader H 2006 Photon-photon coincidences for activity determination: 125I and other

radionuclides Appl. Radiat. Isot. 64 1179 - 85

[5] Schrader H and Walz K. F 1987 Standardization 125I by Photon-photon coincidences counting

and efficiency extrapolation Appl. Radiat. Isot. 41 417

[6] Zimmerman B E and Cessna J T 2000 Experimental determinations of commercial 'dose

calibrator' setting for nuclides used in nuclear medicine Appl. Radiat. Isot. 52 615 - 619

Acknowledgments

This activity is funded by DIPA budget of PTKMR-BATAN in 2013-2014 fiscal. The author would like to thank the Government of Indonesia, especially the leaders of all ranks BATAN which has provided the opportunity to successfully complete this study.