• Title/Summary/Keyword: Ir-192 선원

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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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    • v.39 no.2
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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.

Anisotropy in a Few mm Regions from an Ir192 High Dose Rate Source Measured with a GafChromic Film in Acrylic Phantom (아크릴 팬톰에서 GafChromic 필름을 이용한 고선량률 근접 치료용 Ir-192 선원의 근접 거리에서 비등방성 측정)

  • Huh, Hyun-Do;Kim, Seong-Hoon;Park, Jin-Ho;Cho, Byung-Chul;Shin, Dong-Oh;Soo il Kwon;Chun, Ha-Chung;John J K Loh;Kim, Woo-Chul
    • Progress in Medical Physics
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    • v.15 no.2
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    • pp.94-99
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    • 2004
  • Radiochromic film has several advantages; high spatial resolution, relatively low spectral sensitivity, near tissue equivalence and requires no special development procedure. The object of this study was to measure the anisotropy of an Ir-192 source (microSelectron manufactured by Nucletron) in a few mm regions from the source, using the GafChromic film. The GafChromic film was calibrated in the range of 0∼105 Gy, using a 4 MV photon beam, and the anisotropy function measured in an acrylic phantom using the GafChroimic film. The data obtained gave agreement to within 4.4% of the Monte Calro calculation, by J. F. Williamson, at a radial distance of 2.5 mm with polar angles of 50 to 130$^{\circ}$, while a maximum deviation of 17.6% was observed at angles near 140$^{\circ}$and agreement within 3.7% at a radial distance of 5 mm at polar angles between 35 to 150$^{\circ}$ and a maximum deviation of 7.6% was observed at angles near 30$^{\circ}$. A GafChromic film can be used as a more efficient detector for measuring the anisotropy of an HDR $^{192}$ Ir source at close distances than any other detector.

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Radiation Dose Calculation using MIRD TYPE PHANTOM in the Surrounding Organs during Brachytherapy of Breast Cancer (유방암의 근접치료 시 수학적 모의피폭체를 이용한 인접장기의 선량평가)

  • Park, Eun-tae;Kim, Jung-hoon;Im, In-chul
    • 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.

The Development of Air-kerma Strength Calculation Algorithm in Terms of the Absorbed Dose to Water for HDR Ir-192 Source (기준점에서의 물 흡수선량을 이용한 Ir-192 선원의 공기커마 세기 계산을 위한 알고리즘 개발)

  • Huh, Hyun-Do;Kim, Woo-Chul;Loh, John-Jk;Lee, Suk;Lee, Sang-Hoon;Cho, Sam-Ju;Shin, Dong-Oh;Choi, Jin-Ho;Kwon, Soo-Il;Kim, Seong-Hoon
    • Progress in Medical Physics
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    • v.17 no.4
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    • pp.232-237
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    • 2006
  • The aim of this study was to develop the calculation algorithm of source strength of Ir-192 source In terms of the absorbed dose to water instead of an apparent activity (Ci). For this work the Multi Purpose Brachytherapy Phantom(MPBP) was developed, which was designed to locate the source and the chamber precisely at a specific position Inside the water phantom. The reference point of measurement was set at the 5 cm distance along the transverse axis of the source. For a brachytherapy source calibration, the absorbed dose to water calibration factor ($N_{D.W.Q}$) of an lonization chamber were determined and then apply standard protocols of absorbed dose to water. The calibration factor ($N_{D.W.Q}$) of the ion chamber (TM30013, PTW, Germany) was determined using the EGSnrcCPP Monte Carlo Code. The calculated calibration factor ($N_{D.W.Q}$) was 5.28 cGy/nC. The calculated factor was then used to determine the absorbed dose to water from which the air kerma strength for an Ir-192 source can be easily derived at the reference point (5 cm). The calculated air kerma strength showed discrepancies of -0.6% to +1.8% relative to the air kerma strength provided by the vendor, In this work we demonstrated that the air kerma strength ($S_k$) could be determined from the absorbed dose to water calibration factor for Ir-192 source. In audition, this source calibration method could be applied directly to the dose Calculation formalism of AAPM report TG-43.

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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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    • v.13 no.4
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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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Chamber to Chamber Variations of a Cylindrical Ionization Chamber for the Calibration of an $^{192}Ir$ Brachytherapy Source Based on an Absorbed Dose to Water Standards (물흡수선량 표준에 기반한 $^{192}Ir$ 근접치료 선원 교정 시 원통형 이온함의 이온함 간 변화)

  • Kim, Seong-Hoon;Huh, Hyun-Do;Choi, Sang-Hyun;Kim, Chan-Hyeong;Min, Chul-Hee;Shin, Dong-Oh;Choi, Jin-Ho
    • Progress in Medical Physics
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    • v.20 no.1
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    • pp.7-13
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    • 2009
  • This work is for the preliminary study for the calibration of an $^{192}Ir$ brachytherapy source based on an absorbed dose to water standards. In order to calibrate brachytherapy sources based on absorbed dose to water standards using a clyndirical ionization chamber, the beam quality correction factor $k_{Q,Q_0}$ is needed. In this study $k_{Q,Q_0}s$ were determined by both Monte carlo simulation and semiexperimental methods because of the realistic difficulties to use primary standards to measure an absolute dose at a specified distance. The 5 different serial numbers of the PTW30013 chamber type were selected for this study. While chamber to chamber variations ran up to maximum 4.0% with the generic $k^{gen}_{Q,Q_0}$, the chamber to chamber variations were within a maximum deviation of 0.5% with the individual $k^{ind}_{Q,Q_0}$. The results show why and how important ionization chambers must be calibrated individually for the calibration of $^{192}Ir$ brachytherapy sources based on absorbed dose to water standards. We hope that in the near future users will be able to calibrate the brachytherapy sources in terms of an absorbed dose to water, the quantity of interest in the treatment, instead of an air kerma strength just as the calibration in the high energy photon and electron beam.

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Derivation of Photon Energy Fluence and Mass Energy Absorption Coefficient for 1 Gy Absorbed Dose of Water in Brachytherapy using Ir192 Source (Ir192 선원을 이용한 근접치료에서 물 흡수선량 1 Gy에 대한 광자에너지 플루언스와 질량에너지흡수계수 유도)

  • Kim, Jong-Eon;Ahn, Il-Hoon
    • Journal of the Korean Society of Radiology
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    • v.16 no.1
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    • pp.61-66
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    • 2022
  • The purpose of this study is to derive photon energy fluence and mass energy absorption coefficient for 1 Gy of absorbed dose of water in brachytherapy using an Ir192 source. From the radiotherapy physics written by Khan, the half-value of lead for the gamma ray beam of the Ir192 source was obtained. The linear attenuation coefficient and the mass attenuation coefficient were calculated from the obtained half-value layer of lead. By matching the calculated lead mass attenuation coefficient with the NIST mass attenuation coefficient data, the photon energy of the matching mass attenuation coefficient was determined as the effective energy. By matching the determined effective energy with the photon energy of the NIST data on the mass energy absorption coefficient of water, the mass energy absorption coefficient of water was obtained as 0.03273 cm2/g(32.73 cm2/kg). The photon energy fluence was calculated as 0.03055 J/cm2 by dividing the obtained mass energy absorption coefficient (32.73 cm2/kg) by the absorbed dose of water 1 Gy.

Real Time On-line Quality Assurance System for HDR Brachytherapy (고선량률 근접 방사선 치료를 위한 실시간 온-라인 정도 관리(QA) 시스템 개발)

  • Lee Su Jin;Lee Re Na;Yi Byang Yang;Lim Sang Waak;Choi Jin Ho
    • Progress in Medical Physics
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    • v.15 no.3
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    • pp.156-160
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    • 2004
  • An essential quality assurance (QA) procedure in high dose rate (HDR) remote after-loading brachytherapy is that of the verification of the Ir-192 HDR source positioning accuracy. A number of methods using mechanical rulers or autoradiograph and video cameras have been reported to check the positional error of the Ir-192 source. In this study, the feasibility of a CMOS (Complementary Metal Oxide Semiconductor) PC camera, with a fluorescent screen, was investigated. The agreement between the planned and measured dwell position was better than 1 mm and dwell times better than 0.4 sec. Our results indicate that the CMOS PC camera system could be used as a QA tool for the on-line determination of the source position and dwell time.

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Evaluation of luminance performance of scintillating film for monitoring the position of a radioactive source in an NDT apparatus (비파괴검사 장치 내 방사선원 위치감시용 섬광필름의 발광성능 평가)

  • Lee, Kyung-Jin;Yun, Jeong-Ick;Park, Byung-Gi;Kim, Sin;Lee, Bong-Soo
    • Journal of radiological science and technology
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    • v.28 no.1
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    • pp.13-17
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    • 2005
  • In domestic nondestructive testing(NDT) field, there have recently been radiation exposure accidents due to a disregard for confirmation of the position of radioisotope during the test. In order to prevent these kinds of accidents, a scintillating film has been developed. The scintillating film that can convert gamma-ray to visible light has a function of the position detection of radioisotope in a opaque guide tube of an NDT apparatus. The aim of this study is to enhance the visibility performance of the scintillating film and find out the best configuration of the scintillating film. In order to find appropriate materials for the scintillating film, various inorganic scintillating materials were evaluated in this work. An absolute luminance of the scintillating films was measured by luminance meter for evaluation of visibility performance. Ir-192 gamma projector was used for NDT apparatus. The experiment shows that the scintillating film with reflective layer was the more effective performance for visibility. The higher mixing ratio of scintillating material to binding material, the higher luminance was measured. $Gd_2O_2S(Tb)$ inorganic powder as the scintillating materials had the best performance for visibility of the scintillating film. The developed scintillating film helps to ensure safer environment to the operators.

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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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    • v.35 no.1
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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 $^{192}Ir$.