• 제목/요약/키워드: 이리듐 선원

검색결과 9건 처리시간 0.018초

Study on the Dose Calculation for Iridium and Cessium Sources (이리듐과 세슘의 혼합선원을 이용한 강내치료의 선량계획에 관한 연구)

  • Kang, Jeong-Ku;Kim, Soo-Kon
    • Proceedings of the Korean Society of Medical Physics Conference
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    • 한국의학물리학회 2005년도 제30회 춘계학술대회
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    • pp.42-46
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    • 2005
  • The Dose calculation program for the Buchler remote after-loading system was developed. We use iridium source for the tandem and cessium for the ovoids. We determined the source length and distributions by dividing the program disk to 72 points. The dose rate for the each program disk were calculated and stored to the tables for the xy coordinates. The dose rate for the interesting points for the patients were calculated by using these tables. We also made isodose curve from the calculations. By using the program, we could calculate the dose rate for the various points of the patient quickly and accurately.

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Comparison of Treatment Planning on Dosimetric Differences Between 192Ir Sources for High-Dose Rate Brachytherapy (고선량률 근접치료에서 이리듐-192 선원의 선량특성 차이에 관한 치료계획 비교)

  • Yang, Oh-Nam;Shin, Seong Soo;Ahn, Woo Sang;Kim, Dae-Yong;Kwon, Kyung-Tae;Lim, Cheong-Hwan;Lee, Sang Ho;Choi, Wonsik
    • Journal of radiological science and technology
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    • 제39권2호
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    • pp.163-170
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    • 2016
  • To evaluate whether the difference in geometrical characteristics between high-dose-rate (HDR) $^{192}Ir$ sources would influence the dose distributions of intracavitary brachytherapy. Two types of microSelectron HDR $^{192}Ir$ sources (classic and new models) were selected in this study. Two-dimensional (2D) treatment plans for classic and new sources were generated by using PLATO treatment planning system. We compared the point A, point B, and bladder and rectum reference points based on ICRU 38 recommendation. The radial dose function of the new source agrees with that of the classic source except difference of up to 2.6% at the nearest radial distance. The differences of anisotropy functions agree within 2% for r=1, 3, and 5 cm and $20^{\circ}$ < ${\theta}$ < $165^{\circ}$. The largest discrepancies of anisotropy functions reached up to 27% for ${\theta}$ < $20^{\circ}$ at r=0.25 cm and were up to 13%, 10%, and 7% at r=1, 3, and 5 cm for ${\theta}$ > $170^{\circ}$, respectively. There were no significant differences in doses of point A, point B, and bladder point for the treatment plans between the new and classic sources. For the ICRU rectum point, the percent dose difference was on average 0.65% and up to 1.0%. The dose discrepancies between two treatment plans are mainly affected due to the geometrical difference of the source and the sealed capsule.

Development of Phantom for Evaluate the Suitability of Ir-192 HDR Source with Brachytherapy Tools (근접치료용 하나로 생산 Ir-192 선원의 임상기기 적합성평가용 팬톰개발)

  • Shin, Kyo Chul;Choi, Sang Gyu;Kim, Ki Hwan;Son, Kwang Jae;Jeong, Dong Hyeok;Kim, Jeung Kee
    • Progress in Medical Physics
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    • 제24권3호
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    • pp.171-175
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    • 2013
  • Applicator of various kind of number ten kinds is used to raise from efficiency of brachytherapy to maximum. The compatibility of radiation source and applicator is very important subject for safety brachytherapy. Developed high dose rate brachytherapy source through Hanaro nuclear reactor in Korea Atomic Energy Research Institute and improve compatibility with using equipment in present. In this research, we wished to evaluate stability mechanical safety of radiation source and we developed phantom for evaluate several quality about Ir-192 sealed source that improve newly in Korea Atomic Energy Research Institute and is improved. The result for suitability of Ir-192 HDR source with brachytherapy tools that did normal operation in 2.2~2.7 cm extent about change of equal curvature and consider change of sudden curvature that did normal operation in radius 1.5~1.8 cm extent.

Development of $^{192}Ir$ Small-Focal Source for Non-Destructive Testing Application by Using Enriched Target Material (고농축 표적을 이용한 비파괴검사용 $^{192}Ir$ 미세초점선원 개발)

  • Son, K.J;Hong, S.B.;Jang, K.D.;Han, H.S.;Park, U.J.;Lee, J.S.;Kim, D.H.;Han, K.D.;Park, C.D.
    • Journal of the Korean Society for Nondestructive Testing
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    • 제27권1호
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    • pp.31-37
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    • 2007
  • A $^{192}Ir$ small-focal source has been developed by using the HANARO reactor and the radioisotope production facility at the Korea Atomic Energy Research Institute (KAERI). The small-focal source with the dimension of 0.5 mm in diameter and 0.5 mm in length was fabricated as an aluminum-encapsulated form by a specially designed pressing equipment. For the estimation of the radioactivity, neutron self-shielding and ${\gamma}-ray$ self-absorption effects on the measured activity was considered. From this estimation, it is realized that $^{192}Ir$ small-focal sources over 3 Ci activities can be produced from the HANARO. Field performance tests were performed by using a conventional source and the developed source to take images of a computer CPU and a piece of a carbon steel. The small-focal source showed better penetration sensitivity and geometrical sharpness than the conventional source does. It is concluded from the tests that the focal dimension of this source is small enough to maximize geometrical sharpness in the image taking for the close proximity shots, pipeline crawler applications and contact radiography.

Comparison of Calibration Methods of $^{192}\textrm{Ir}$ Sources for High Dose Rate Brachytherapy (고선량률 근접조사치료용 이리듐-192 방사성동위원소의 교정방법 비교연구)

  • Huh Hyun Do;Park Sung Yong;Lee Rena J;Shin Dong Oh;Kwon Soo Il;Loh John J K;Choi Jinho
    • Progress in Medical Physics
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    • 제15권4호
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    • pp.192-196
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    • 2004
  • The activity of Ir-192 sources for high dose rate (HDR) Brachytherapy in Korea were measured by using the well-type chamber and using the calibration Jig with the Farmer-type ionization chamber to compare the manufacturer certificated source strength which is supplied with each new Ir-192 source. The activity of two different source models used in six hospitals were measured. The range of measured activities to the manufacturer's suggested ones was -2.40% to +3.31% for the calibration Jig and -3.12% to 0.00% for the well-type chamber system. The source strength values given by the manufacturer for the 6 sources were within ${\pm}5%$ for the two different measuring equipment. Our results demonstrate that well-type chamber as wall as Farmer-type chamber system are appropriate system for the routine source calibration procedures in HDR brachytherapy. Whenever a new source is installed to use in clinics, a source calibration should be carried out.

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Monte Carlo Simulation for Dose Distributions from Ir-192 in Brachytherapy (근접 방사선치료용 이리듐 선원의 선량분포에 대한 몬데칼로 시뮬레이션)

  • 김승곤;강정구;이정옥;정동혁;문성록
    • Progress in Medical Physics
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    • 제13권4호
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    • pp.187-194
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    • 2002
  • In this work we investigated through Monte Carlo calculations the physical characteristics of the absorbed dose from the Ir-192 source used in brachytherapy The Monte Carlo calculations were performed using the code EGS4, which was extensively modified in order to handle cylindrical sources, phantoms, and energy distributions to suit out own purpose. From the results of the calculations for the $\beta$ -rays, it was found that they contribute on the average 0.02% to The total absorbed dose in the distance range of 0.5-5.0 cm from the source. This is due to the face that, although most of the primary $\beta$ -rays are absorbed in the source and encapsulation material, the resulting low energy braking radiation from them contribute to such a distance. The absorbed dose in the encapsulation material varied on the average from 2.8% for platinum down to 1.1% for iron. The radial dose functions obtained by our Monte Carlo calculations were consistent within $\pm$3% with those of the TG-43 report for the radial distance interval 0.5-10.0 cm from the source. The user code we wrote in this work can be used for other sources of different sizes and so it can be very useful in designing and producing the sources for brachytherapy.

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Quality Correction for Ir-192 Gamma Rays in Air Kerma Strength Dosimetry Using Cylindrical Ionization Chambers (원통형 전리함을 이용한 Ir-192 선원에 대한 공기커마세기 측정 시 선질보정에 관한 연구)

  • Jeong, Dong-Hyeok;Kim, Jhin-Kee;Kim, Ki-Hwan;Oh, Young-Kee;Kim, Soo-Kon;Lee, Kang-Kyoo;Moon, Sun-Rock
    • Progress in Medical Physics
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    • 제20권1호
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    • pp.30-36
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    • 2009
  • The quality correction in the air kerma dosimetry for Ir-192 using farmer type ionization chambers calibrated by Co-60 quality is required. In this study we determined quality factor ($k_u$) of two ionization chambers of PTW-N30001 and N23333 for Ir-192 source using dosimetric method. The quality factors for energy spectrum of microSelectron were determined as $k_u$=1.016 and 1.017 for PTW-N30001 and N23333 ionization chambers respectively. We applied quality factors in air kerma dosimetry for microSelectron source and compared with reference values. As a results we found that the differences between reference air kerma rate and measured it with and without quality correction were about -0.5% and -2.0% respectively.

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Comparison of Non-Destructive Testing Images using $^{192}Ir$ and $^{75}Se$ with Computed Radiography System (Computed Radiography 시스템에 $^{192}Ir$$^{75}Se$ 동위원소를 적용하여 촬영한 비파괴검사 영상 비교)

  • Kang, Sang-Mook;Chol, Chang-Il;Lee, Seung-Kyu;Park, Sang-Ki;Kim, Yong-Kyun
    • Journal of Radiation Protection and Research
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    • 제35권1호
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    • pp.26-33
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    • 2010
  • A computed Radiography (CR) system by use of reusable Image Plate (IP) offers a convenient and reliable way to replace a conventional film-screen system for NDT (non-destructive testing) field. The quality of a radiography to detect a defect of welded objects depends on the procedure embracing several factors such as measurement conditions, image plate type/class, radiation energy, radiation type, and source to image plate distance. Also, the ability of images to detect a flaw reduces with increasing object thickness. In the study, the properties of gamma ray source were summarized for NDT field and inspection images of CR image system manufactured by FUJI were acquired using $^{75}Se$ and $^{192}Ir$ with welded objects. We analyzed the gray scale of hole defect image by using XCAP image processing program and calculated the image contrast and SNR in definition. Also the sesitivities of image quality indicator(IQI) were calculated for hot and cooling tube image of $^{75}Se$ and $^{192}Ir$.

Evaluation of Absorbed Dose for the Right Lung and Surrounding Organs of the Computational Human Phantom in Brachytherapy by Monte Carlo Simulation (근접방사선치료 시 몬테카를로 전산모사를 이용한 인체전산팬텀의 우측 폐와 주변 장기 선량평가)

  • Lee, Jun-Seong;Kim, Yang-Soo;Kim, Min-Gul;Kim, Jung-Soo;Lee, Sun-Young
    • Journal of radiological science and technology
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    • 제43권6호
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    • pp.443-451
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    • 2020
  • This study is to evaluate absorbed dose from right lung for brachytherapy and to estimate the effects of tissue heterogeneities on dose distribution for Iridium-192 source using Monte Carlo simulation. The study employed Geant4 code as Monte Carlo simulation to calculate the dosimetry parameters. The dose distribution of Iridium-192 source in solid water equivalent phantom including aluminium plate or steel plate inserted was calculated and compared with the measured dose by the ion chamber at various distances. And the simulation was used to evaluate the dose of gamma radiation absorbed in the lung organ and other organs around it. The dose distribution embedded in right lung was calculated due to the presence of heart, thymus, spine, stomach as well as left lung. The geometry of the human body was made up of adult male MIRD type of the computational human phantom. The dosimetric characteristics obtained for aluminium plate inserted were in good agreement with experimental results within 4%. The simulation results of steel plate inserted agreed well with a maximum difference 2.75%. Target organ considered to receive a dose of 100%, the surrounding organs were left the left lung of 3.93%, heart of 10.04%, thymus of 11.19%, spine of 12.64% and stomach of 0.95%. When the statistical error is performed for the computational human phantom, the statistical error of value is under 1%.