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Determining profile of dose distribution for Pd-103 brachytherapy source

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DETERMINING PROFILE OF DOSE DISTRIBUTION FOR PD-103

BRACHYTHERAPY SOURCE

B. Camgöz1, G. Yeğin2, M. N. Kumru1

!Ege University Nuclear Sciensec Institute bornova- Izrrrir/TURKEY, 2Celal Bayar University Physics Dept. Manisa/TURKEY

1. INTRODUCTION

Palladium radioisotope is LDR (Low radiation Dose Rate) source. Main radioactive material was coated with titanium cylinder with 3mm length, 0.25mm radius. There are two parts of Pd-103 in the titanium cylinder. It is impossible to investigate differential effects come from two part as experimental. Because, the source dimensions are small comparatively measurement distances. So there is only simulation method. In dosimetric studies it is aimed to determine absorbed dose distribution in tissue as radial and angular.

In nuclear physics it is obligation to use computer based methods for researchers. Radiation studies have hazards for scientist and people interacted with radiation. When hazard exceed over recommended limits or physical conditions are not suitable (long work time, non economical experiments, inadequate sensitivity of materials etc.) it is unavoidable to simulate works and experiments before practices of scientific methods in life. In medical area, usage of radiation is required computational work for cancer treatments. Some computational studies are routine in clinics and other studies have scientific development purposes.

In design of a new brachytherapy source it is important to consider detailed contributions from all source components. In experiments it is impossible to determine inner factors of source rather than inadequate conditions.

In Pd-103 sample we obtained differential parameters. Using this data it will be easier to concept new source models. Separate calculations are agreed with accepted literature values acquired from massive calculations. In tissue dose distribution can be shaped more sensitive with this method. To do just computer simulation is available.

There are massive sources (1-125, Ir-192, etc.). Same process should be done by cutting the source into many radioactive parts in virtual experiments. This is the novel approach for sensitive database to use it in practical clinical treatments.

2. MATERIAL AND METHOD

In the capsule there are two radioactive partitions. Therefore total dose includes two contributions. Dose profile will be different comparatively massive (or single) source. Separate doses will be affect dose distribution around the source. Dose can be written as:

Diotai = D!+D2, as generalized DTotal = ZD,

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Source 1 Marker Source2

Figure 1. Dose points along Z axis of capsule on R levels (distances)

Doses were calculated using Monte Carlo method so the data of dose distribution is relative. This values are used in fraction so real dose is not needed. In Monte Carlo code dos is calculated in unit Gray/foton (generaly; Gray/particle). So the important parameters are dosimetric characteristics and dose distribution profile.

Figure 2. At R=0.1cm dose distribution along capsule

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Figure 3. At R=0 5cm dose distribution along capsule c o o >• CD 1E-13 <D O Û 5E-14 0 m -■ Right ■Left Total 0 0,05 0,1 0,15 0,2 0,25 Z (cm)

Figure 4. At R=lcm dose distribution along capsule

C o > CD <D O Û 1.5E-14 1E-14 5E-15 0 0,05 0,1 0,15 Z (cm) -Right ■Left Total 0,2 0,25

Figure 5. At R=2cm dose distribution along capsule 0

Calculations were performed for R= 0.1, 0.5, 1, 2cm on [0, z]. At R distance larger than 1cm, dos distribution shape is seems independent on seperate source effect. This graphics are symmetric because of the complate source is symmetrik around R and Z axis in cylindrical coordinates. Resits are symmetrik on [0, -z]

3. CONCLUSION

Along capsule length on Ri lines dose distribution shape is different for small R (0.1 - 0.5cm) unlike normal distances [ 1cm - R]. It is important to determine dose in smal distances. Because dose shows rapid changes in this interval. Seperation of two source is responsible of the dose profile directly. This is effective in small radial region. At larger distance the effect cannot be seem. It is momentous designing of LDR sources for smal distance. Cancerous tissues will be mostly irradiated in this regions.

4. REFERENCES

1. Ernesto Mainegra, Roberto Capote Ernesto Lopez,2000 Radial Dose Function for 103Pd, 1251, 169Yb and 192Ir Brachytherapy Sources. Phys. Med. Biol 45:703—717

Ernesto Mainegra, Roberto Capote Ernesto Lopez, 2001. Amzotropy Functions for Low Energy Interstitial Brachytherapy Sources: An EGS4 Monte Carlo Study. Phys. Med. Biol 46.135-150

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2. J.R. Clark, H. Zhang, V. Rachabatthula, R.A. J.R. Clark,. Zhang, V. Rachabatthula, R.A. Koona, A.S. Meigooni Koona, A. S. Meigooni University o f Kentucky Chandler Medical Center, University of Kentucky Chandler Medical Center, Department o f Radiation Medicine, Department o f Radiation Medicine, Lexington, Kentucky 40536 Lexington, Kentucky 40536-00840084

3. Jeffrey F. Williamson,Overview of Update of AAPM Task GroupNo. 43 Report - A Revised AAPM Protocol for Interstitial Brachytherapy DoseCalculations., Radiation Oncology PhysicsVirginia Commonwealth University

4. Kazuro Iwatal, Ning J Yue2 and Ravinder 2004, Two-dimensional dosimetry in the near field of the model 200 103Pd source for interstitial brachytherapy implants using a thermoluminescent sheet. NathPhys. Med. Biol. 49 (2004) 4049-4063

5. Mark J. Rivard, Bert M. Coursey, Larry A. DeWerd, William F Hanson, 2004. Update of AAPM Task Group NO. 43 Report: A Resvised AAPM Protocol for Brachytherapy Dose Calculations. Med. Phys. 31.663-674 6. S Bernard and S Vynckier 2005, Dosimetric study of a new polymer encapsulated palladium-103 seed. Phys.

Med. Biol. 50 (2005) 1493-1504

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