• Progress in Medical Physics
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• v.23 no.4
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• pp.326-332
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• 2012

Recently, there are difficulties in operating brachtherapy machine in the radiotherapy department because of increasing the source price with decreasing nuclear reactor in the world. The development and technical features of the Ir-192 HDR sources (4.5 mm, 1.1 mm in diameter) in Korea were described in this report. We expect that this report will be helpful for hospitals to make the long-term plan for operating and managing HDR brachytherapy machine.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.373-378
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• 1997

시험가동중인 다목적연구용 '하나로'를 이용하여 근접치료용으로 사용되는 $^{192}$ IR seed 제조실험을 하였다. '하나로'의 특성을 고려하여 제작된 조사표적용기에 표적용 Ir seed를 넣고 밀봉한 후 He 누출시험을 통과한 표적만 원자로의 HTS 조사공에서 중성자 조사시켰다. HTS 조사공의 평균 열중성자속은 측정결과 원자로출력 15 MWt일 때 2.54 $\times$ $10^{13}$ n/$\textrm{cm}^2$.sec였다. 5회에 걸쳐 5개의 조사표적을 사용하여 총 200개의 $^{192}$ Ir seed를 제조, 실험하였으며 2시간 조사후 14일간 냉각시킨 Ir seed의 r-ray spectrum을 분석한 결과 $^{l92}$Ir외의 불순핵종은 검출되지 않았다. Ir seed의 방사능은 이온전리함을 사용하여 측정하였으며 방사능 측정결과 개별 $^{192}$ Ir seed의 방사능값은 평균 방사능값으로부터 $\pm$5 % 이내오차의 방사능 균일도를 갖는 것이 확인되었다.차의 방사능 균일도를 갖는 것이 확인되었다.

• Progress in Medical Physics
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• v.14 no.2
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• pp.81-89
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• 2003

The dose distributions of designed Ir-192 micro-source were investigated by dose computations which were accomplished by employing shape of encapsule material and thickness of the source for self-absorption. The computation dose derived from air-kerma rate (S$_{k}$ ) and dose rate constant (Λ) includes the anisotropy of dose distribution around the source. We got the dose rate constants in a water medium is 1.154 cGy h$^{-1}$ U$^{-1}$ . The size of the source was 0.5 mm in diameter and 3.5 mm in length and it was encapsuled in 1.1 mm$\Phi$${\times}$5.5 mm of stainless steel sealed with 0.3 mm of filter thickness. The tissue dose of reference point at 1.0 cm radial distance of the source axis was delivered 1.154 Uh$^{-1}$ (1.3167${\times}$10$^{-3}$ cGy/mCi-sec) from the S$_{k}$ 4.108U/mCi of Ir-192 source. The filtration effect contributed to air-kerma strength as exponential filtering effect of 86.2% in total attenuation, but self-absorption was 88.4% from radial dose distributions. In particular, the dose attenuations showed a rapid anisotropic distributions as 56% of reference dose along to $\pm$10 degrees from the tip of source axis and 50% for of that to source-cable direction. We persist in use the large diameter of applicator will avoid the dose anisotropy by the filtered attenuation effects along the axis of Ir-192 micro-source.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.752-756
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• 1998

산업용 및 의료용으로 사용되는 $^{192}$ Ir 방사선원에 대한 $\psi$선 자기흡수효과인자를 실험을 통하여 구하였다. 이를 위하여 3 mm $\psi$ x 3 mm t, 2.5 mm $\psi$ x 2.5 mm t, 2 mm $\psi$ x 2 mm Ir의 원주형 Ir 표적과 3 mm $\psi$ x 0.25 mm t, 3 mm $\psi$ x 0.1 mm t의 원판형 Ir 표적을 하나로의 PTS(Pneumatic Transport System)조사공에서 중성자 조사하였다. 이온전리함을 사용하여 각 Ir 표적의 방사능을 측정하고 계산에 의해서 구한 생성방사능 값과의 비를 구하는 방법으로 $^{192}$ Ir의 ${\gamma}$선 자기흡수효과인자를 구하였다. 이 값들은 원주형 표적에 대하여 각각 0.614, 0.687, 0.704 였고 원판형 표적에 대하여 각각 0.827, 0.875 였다. 원주형 Ir 표적내부의 중성자 자기흡수효과의 정도를 알아보기 위하여 2.5 mm $\psi$ x 0.25 mm t Ir 표적 10장을 포개어 중성자 방사화시킨 후 각 표적의 방사능을 측정한 결과 가장 바깥쪽 표적의 방사능이 중심부에 위치한 표적보다 약 2배정도 방사화가 많이 일어남을 알 수 있었다. 이번에 구한 ${\gamma}$선 자기흡수효과인자는 향후 산업용 및 의료용으로 사용되는 $^{192}$ Ir 방사선원의 사용자에게 제공되는 최종방사능을 평가하는데 유용하게 사용될 수 있다.

• Progress in Medical Physics
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• v.9 no.1
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• pp.55-64
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• 1998

In recent, the demand of development of the high dose rate brachytherapy source increased for substitute for Co-60 source by iridium source, since the supplying Co-60 source is very depressed and the high dose rate brachytherapy sources are entirely imported from the abroad. This study investigated the exposure rates and isotropic dose distributions for the Ir-192 source produced from $\^$191/Ir(n,r)$\^$192/Ir by nuclear reactor in Korea Atomic Energy Research Institute. The activity of source was obtained an 1.012 Ci (the initial activity without encapsulation was 2,87Ci) by measurement with encapsuled stainless steel. The exposure rate of provided Ir-192 source was determined on 6.36 ${\pm}$ 0.147 Rm$^2$/h-GBq (2.350 ${\pm}$ 0.054 Rcm$^2$/mCi-hr) within ${\pm}$ 2.2% discrepancy with IC-10 ion chamber (0.14 cc) which was mounted on the acrylic jig to 5, 10 and 20 cm from the center of source. The calculated doses with 22 most significant spectrum lines were corrected with intrinsic efficiency of the germanium detector were compared to measured exposure dose rates within ${\pm}$3.8 % discrepancy. The authors confirmed the high dose rate Ir-192 source could be replaced the long decayed Co-60 source via investigation of the isotropic dose distributions in lateral, source axis and diagonal direction of source center are very closed to within 3% uncertainties. Especially, this exposure rate constant and isotropic dose distribution will be fundamental to build the high dose rate source and develop the computed therapy planning system.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.757-762
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• 1998

“하나로”를 이용하여 강내 조사용으로 사용되는 $^{192}$ Ir 선원의 제조법을 확립하였다. HTS (Hydraulic Transfer System)조사공에서 48시간 조사한 $\psi$2.5 mm x t 0.25 mm의 원판형 Ir 표적 10장을 쌓아서 방사능이 1.012 Ci인 선원을 시험제조하였다. 선원 제작에 관련된 생성방사능, 중성자 자기홉수효과 인자를 이론적으로 계산하여 시험제조에 사용하였고 ${\gamma}$선 자기흡수효과는 실험으로 측정하여 암 치료에 요구되는 10-20 Ci 선원의 상용생산에 필요한 자료를 확보하였다. 치료용 소선원 제작에 관련된 표적제작, 중성자조사, 방사능 측정, 선원조립, 밀봉용접, 품질관리 등의 제작기술을 확립하고 선원의 안전성은 밀봉시험, 표면오염검사 등을 수행하여 확인하였다. 제조된 선원은 실제 사용되는 조사장치에 장착하여 기능시험을 수행할 것이다. 이번 실험을 통하여 강내 조사용으로 사용되는 10-20 Ci 방사능의 $^{192}$ Ir 선원을 안정적으로 공급할 수 있음을 확인하였으며 하나로를 이용하여 캡슐 직경 4 mm의 치료용 소선원 제작기술을 확립하였다. 개발된 /spp 192/Ir 강내 조사용 선원은 국내 5-6개 병원에 공급할 것이며 이 기술을 바탕으로 직경 1.1-1.6 mm의 강내 조사용 선원도 개발할 예정이다.

• Journal of the Korean Society of Radiology
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• v.10 no.4
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• pp.271-278
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• 2016

This study was fulfilled to evaluate the absorbed dose of breast and adjacent organs using MIRD type phantom in brachytherapy of breast cancer. The absorbed dose was analyzed assuming left or right breast is source organ which is $^{103}Pd$ or $^{192}Ir$. As a result, $^{192}Ir$ dose is higher than $^{103}Pd$ in source organ and also in contralateral breast. Particularly, significant adjacent organs are lung, liver, heart and contralateral breast in brachytherapy of breast cancer.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.430.1-430
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• 2001

• Journal of radiological science and technology
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• v.30 no.1
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• pp.33-38
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• 2007

The propose of this study is a verification of the correct calculation of the dose around source and the prescription dose of Ir-192 source in the plato treatment planning system. The source and orthogonal coordinates for lateral direction and those for the anterior posterior direction were drawn on a A4 paper and then input into the system. The prescription dose was prescribed to two points with radius 1 cm in the direction of polar angle $90^{\circ} and $270^{\circ} from the center of the source. The doses of prescription point and dose points acquired from the treatment planning system were compared with those from manual calculation using the geometry function formalism derived by Paul King et al. In this analysis, the doses of prescription point were exactly consistent with each other and those of dose points were obtained within the error point of 1.85%. And the system of accuracy was evaluated within 2% of tolerance error. Therefore, this manual dose calculation used for the geometry function formalism is considered to be useful in clinics due to its convenience and high quality assurance.

• Progress in Medical Physics
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• v.21 no.1
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• pp.78-85
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• 2010

The compatibility with GammaMed-12i brachytherapy machine for an Ir-192 encapsulated source (IRRS20, KAERI, Korea) manufactured by Korea atomic energy research institute (KAERI) has been investigated. As a mechanical testing of compatibility, precise measurement of step movement with channels, measurement of curvature of radius for wire, and emergency return testing were performed. Periodic measurements of air kerma strength for 45 days were carried out to evaluate decay characteristics of Ir-192 radioisotope and comparison of dose distributions in phantom between KAERI and old sources previously used were performed by film dosimetry. KAERI source has a good compatibility with GammaMed12i machine as a result of mechanical testing. There are in good agreement with calculated values in activity characteristics and there were small differences in dose distributions around the source in comparison between KAERI and old source.