• 제목/요약/키워드: Measurement Radiation dose

검색결과 665건 처리시간 0.035초

Prediction of Midline Dose from Entrance and Exit Dose Using OSLD Measurements for Total Body Irradiation

  • Choi, Chang Heon;Park, Jong Min;Park, So-Yeon;Chun, Minsoo;Han, Ji Hye;Cho, Jin Dong;Kim, Jung-in
    • Journal of Radiation Protection and Research
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    • 제42권2호
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    • pp.77-82
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    • 2017
  • Background: This study aims to predict the midline dose based on the entrance and exit doses from optically stimulated luminescence detector (OSLD) measurements for total body irradiation (TBI). Materials and Methods: For TBI treatment, beam data sets were measured for 6 MV and 15 MV beams. To evaluate the tissue lateral effect of various thicknesses, the midline dose and peak dose were measured using a solid water phantom (SWP) and ion chamber. The entrance and exit doses were measured using OSLDs. OSLDs were attached onto the central beam axis at the entrance and exit surfaces of the phantom. The predicted midline dose was evaluated as the sum of the entrance and exit doses by OSLD measurement. The ratio of the entrance dose to the exit dose was evaluated at various thicknesses. Results and Discussion: The ratio of the peak dose to the midline dose was 1.12 for a 30 cm thick SWP at both energies. When the patient thickness is greater than 30 cm, the 15 MV should be used to ensure dose homogeneity. The ratio of the entrance dose to the exit dose was less than 1.0 for thicknesses of less than 30 cm and 40 cm at 6 MV and 15 MV, respectively. Therefore, the predicted midline dose can be underestimated for thinner body. At 15 MV, the ratios were approximately 1.06 for a thickness of 50 cm. In cases where adult patients are treated with the 15 MV photon beam, it is possible for the predicted midline dose to be overestimated for parts of the body with a thickness of 50 cm or greater. Conclusion: The predicted midline dose and OSLD-measured midline dose depend on the phantom thickness. For in-vivo dosimetry of TBI, the measurement dose should be corrected in order to accurately predict the midline dose.

Analysis of Radiation Exposure Dose according to Location Change during Radiation Irradiation

  • Chang-Ho Cho;Jeong-Lae Kim
    • International Journal of Advanced Culture Technology
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    • 제12권2호
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    • pp.368-374
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    • 2024
  • During an X-ray examination, the beam of radiation is dispersed in many directions. We believe that managing radiation dose is about providing transparency to users and patients in the accurate investigation and analysis of radiation dose. The purpose of measuring the radiation dose as a function of location is to ensure that medical personnel using the equipment or participating in the operating room are minimally harmed by the different radiation doses depending on their location. Four mobile diagnostic X-ray units were used to analyze the radiation dose depending on the spatial location. The image intensifier and the flat panel detector type that receives the image analyzed the dose by angle to measure the distribution of the exposure dose by location. The radiation equipment used was composed of four units, and measuring devices were installed according to the location. The X-ray (C-arm) was measured by varying the position from 0 to 360 degrees, and the highest dose was measured at the center position based on the abdominal position, and the highest dose was measured at the 90° position for the head position when using the image intensifier equipment. The operator or medical staff can see that the radiation dose varies depending on the position of the diagnostic radiation generator. In the image intensifier and flat panel detector type that accepts images, the dose by angle was analyzed for the distribution of exposed dose by position, and the measurement method should be changed according to the provision of dose information that is different from the dose output from the equipment according to the position.

방사선 근접치료에 있어서 핵자기공명영상을 이용한 3차원 방사선 선량분포도의 가시화를 위한 polymer 젤의 이용 (The Use of Polymer Gel for the Visualization of 3-D Dose Distribution in Brachytherapy Using Magnetic Resonance Imaging)

  • 강해진;조삼주;정은기;강승희;오영택;전미선;권수일
    • 한국의학물리학회지:의학물리
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    • 제9권4호
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    • pp.207-215
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    • 1998
  • 방사선의 측정방법으로 현재까지 여러 방법들이 쓰여져 왔다. 여기에는 필름을 이용하는 방법, TLD를 이용하는 방법, 전리함(ion chamber)을 이용하는 방법 등이 대체로 가장 많이 쓰여지는 방법이다. 그러나 본 연구에서는 새로운 방사선측정 방법이 시도되었다. 고분자 젤과 핵자기공명영상 (MRI)을 이용한 방법이 그 것이다. 본 연구의 목적은 방사선 측정을 위한 고분자 젤을 합성하고 합성된 젤을 사용하여 젤의 방사선 흡수선량과의 관계를 MRI 영상으로부터 구해서, 이 결과를 근접치료에 쓰이는 seed 선원의 선량분포를 측정하여 가시화 시키는데 있다. 이를 위해 지름 12 cm 원통형 팬텀에 젤을 합성하고, 이 젤을 뇌정위 방사선수술에 쓰이는 30 mm 콜리메이터를 이용하여 여러 단계의 선량을 젤에 조사하였다. 이렇게 조사된 젤은 MRI 을 촬영하였고 이렇게 촬영된 MRI 영상으로부터 젤팬텀의 각 위치의 횡이완시간 (T$_2$ time)을 영상분석 소프트웨어를 이용하여 계산하였다. 그 결과 젤의 홉수선량과 횡이완시간과는 17 Gy 근처까지는 거의 반비례 ($R^2$=0.993)하는 것을 알 수 있었으며, 이 보다 높은 흡수선량에 대해서는 또 다른 관계가 있음을 알 수 있었다. 또 이것을 이용하여 HDR afterloading system 의 Ir-192 seed 선원에 의한 선량분포와 2 mCi Ir-192 seed 선원에 의한 선량분포를 측정하였다. 그리고 이 것을 각각 치료계획컴퓨터에 의한 선량분포곡선과 비교하였다. 본 연구의 결과로는 고분자 젤을 이용한 방사선의 측정방법을 시도하여 홉수선량과 젤의 특성과의 관계를 밝혔으며, 실제로 그접치료에 쓰이는 seed 선원에 의한 선량분포 곡선을 얻는데 적용하였다.

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Transmission Dose Estimation Algorithm for in vivo Dosimetry

  • Yun, Hyong-Geun;Huh, Soon-Nyung;Lee, Hyoung-Koo;Woo, Hong-Gyun;Shin, Kyo-Chul;Ha, Sung-Whan
    • Journal of Radiation Protection and Research
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    • 제28권1호
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    • pp.59-63
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    • 2003
  • Purpose : Measurement of transmission dose is useful for in vivo dosimetry of QA purpose. The objective of this study is to develope an algorithm for estimation of tumor dose using measured transmission dose for open radiation field. Materials and Methods : Transmission dose was measured with various field size (FS), phantom thickness (Tp), and phantom chamber distance (PCD) with a acrylic phantom for 6 MV and 10 MV X-ray Source to chamber distance (SCD) was set to 150 cm. Measurement was conducted with a 0.6 cc Farmer type ion chamber. Using measured data and regression analysis, an algorithm was developed for estimation of expected reading of transmission dose. Accuracy of the algorithm was tested with flat solid phantom with various settings. Results : The algorithm consisted of quadratic function of log(A/P) (where A/P is area-perimeter ratio) and tertiary function of PCD. The algorithm could estimate dose with very high accuracy for open square field, with errors within ${\pm}0.5%$. For elongated radiation field, the errors were limited to ${\pm}1.0%$. Conclusion : The developed algorithm can accurately estimate the transmission dose in open radiation fields with various treatment settings.

A Review of Dose Rate Meters as First Responders to Ionising Radiation

  • Akber, Aqeel Ahmad;Wiggins, Matthew Benfield
    • Journal of Radiation Protection and Research
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    • 제44권3호
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    • pp.97-102
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    • 2019
  • Background: Dose rate meters are the most widely used, and perhaps one of the most important tools for the measurement of ionising radiation. They are often the first, or only, device available to a user for an instant check of radiation dose at a certain location. Throughout the world, radiation safety practices rely strongly on the output of these dose rate meters. But how well do we know the quality of their output? Materials and Methods: This review is based on the measurements 1,158 commercially available dose rate meters of 116 different makes and models. Expected versus the displayed dose patterns and consistency was checked at various dose rates between $5{\mu}Gy{\cdot}h^{-1}$ and $2mGy{\cdot}h^{-1}$. Samples of these meters were then selected for further investigation and were exposed to radiation sources covering photon energies from 50 keV to 1.5 MeV. The effect of detector orientation on its reading was also investigated. Rather than focusing on the angular response distribution that is often reported by the manufacturer of the device, this study focussed on the design ergonomics i.e. the angles that the operator will realistically use to measure a dose rate. Results and Discussion: This review shows the scope and boundaries of the ionising radiation dose rate estimations that are made using commonly available meters. Observations showed both inter and intra make and model variations, occasional cases of instrument failure, instrument walk away, and erroneous response. Conclusion: The results indicate the significance of selecting and maintaining suitable monitors for specific applications in radiation safety.

국립공원의 해발고도에 따른 환경방사선 측정 (Measurement of Environmental Radiation according to Altitude above Sea Level in National Park)

  • 지태정;이인식
    • 한국콘텐츠학회논문지
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    • 제12권12호
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    • pp.694-701
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    • 2012
  • 본 연구는 국가환경방사선 자동감시망이 설치되지 않은 국립공원의 산악 지역을 대상으로 환경방사선을 측정하였다. 측정 방법은 지표 1m 높이에서 공간선량과 지표면에서의 지표선량을 측정하였다. 국립공원 선정은 중부지역과 남부지역을 같은 분포로 하여 전국에 10곳을 선정하였다. 측정장비는 감마선측정에 활용되는 INTERCEPTOR$^{TM}$(Thermo, USA, 2006)를 사용하였다. 방사선측정은 국립공원 입구와 정상에서는 필수적으로 측정하였고, 그 외 지점은 해발 고도를 500m 단위로 구분하여 탐방객이 많이 다니는 곳에서 측정하였다. 측정횟수는 각 지점에서 2분간 장비를 안정시킨 후 5회 이상 측정하였다. 측정결과, 공간감마선량의 경우 1,000m 이하 국립공원에서는 해발 고도 500m 지점에서 높은 선량이 측정되었다. 그 중 북한산, 계룡산, 월출산에서 $0.23{\mu}Svh^{-1}$ 이상인 것으로 확인되었다. 1,000m 이상의 국립공원에서는 설악산 1,500m 지점에서 $1.77{\mu}Svh^{-1}$로 측정되어 백그라운드 기준 선량보다 10배 이상 증가하였다. 선량에 유의한 변화를 보이지 않은 국립공원은 내장산, 소백산, 지리산으로 확인되었다. 환경방사선량이 낮게 측정된 산은 가야산 정상(1,430m)에서 $0.04{\mu}Svh^{-1}$, 한라산 정상(1,950m)에서 $0.03{\mu}Svh^{-1}$인 것으로 확인되었다. 지표선량 측정에서도 중간 높이인 500m, 1,000m에서 높게 측정되었다. 지각 구성물질의 종류에 따른 측정에서는 암석으로 구성된 국립공원에서 높은 선량으로 조사되었으며, 화산활동이 일어났던 한라산에서는 환경방사선량이 낮게 측정되었다.

Radiation Exposure Dose of Handlers Using 18F-FDG in Small Animal Image Acquisition Experiments

  • Ik Soo Kim;Sun Young Yoon;Hwa Yeon Yeo
    • 방사선산업학회지
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    • 제17권3호
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    • pp.233-238
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    • 2023
  • This study was conducted to confirm the safety of the operator's radiation exposure in the micro PET-CT image acquisition experiment using the 18F-FDG. The usage of 18F-FDG and the exposure dose of handlers were measured at University B in Metropolitan City A, which uses 18F-FDG for micro PET-CT image acquisition. As a result of the measurement, the exposure dose is far below the effective dose limit of radiation workers, 50 mSv per year, and the equivalent dose limit of 500 mSv per year for hands, feet, and skin. has been measured Since these exposure doses can be further increased according to the number of times of use of 18F-FDG, it is judged that the exposure dose compared to the handling amount of 18F-FDG shown in this study can be used as reference data. In addition, as changed environments such as the use of materials other than unopened RI are occurring in education and research environments, such as the use of 18F-FDG at University B, radiation exposure with more interest in safety management by checking the factors of radiation exposure of the handler concerned We will always do our best to reduce it.

Evaluations of a Commercial CLEANBOLUS-WHITE for Clinical Application

  • Geum Bong Yu;Jung-in Kim;Jaeman Son
    • 한국의학물리학회지:의학물리
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    • 제35권1호
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    • pp.10-15
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    • 2024
  • Purpose: This study aimed to comprehensively investigate the diverse characteristics of a novel commercial bolus, CLEANBOLUS-WHITE (CBW), to ascertain its suitability for clinical application. Methods: The evaluation of CBW encompassed both physical and biological assessments. Physical parameters such as mass density and shore hardness were measured alongside analyses of element composition. Biological evaluations included assessments for skin irritation and cytotoxicity. Dosimetric properties were examined by calculating surface dose and beam quality using a treatment planning system (TPS). Additionally, doses were measured at maximum and reference depths, and the results were compared with those obtained using a solid water phantom. The effect of air gap on dose measurement was also investigated by comparing measured doses on the RANDO phantom, under the bolus, with doses calculated from the TPS. Results: Biological evaluation confirmed that CBW is non-cytotoxic, nonirritant, and non-sensitizing. The bolus exhibited a mass density of 1.02 g/cm3 and 14 shore 00. Dosimetric evaluations revealed that using the 0.5 cm CBW resulted in less than a 1% difference compared to using the solid water phantom. Furthermore, beam quality calculations in the TPS indicated increased surface dose with the bolus. The air gap effect on dose measurement was deemed negligible, with a difference of approximately 1% between calculated and measured doses, aligning with measurement uncertainty. Conclusions: CBW demonstrates outstanding properties for clinical utilization. The dosimetric evaluation underscores a strong agreement between calculated and measured doses, validating its reliability in both planning and clinical settings.

Guideline on Acceptance Test and Commissioning of High-Precision External Radiation Therapy Equipment

  • Kim, Juhye;Shin, Dong Oh;Choi, Sang Hyoun;Min, Soonki;Kwon, Nahye;Jung, Unjung;Kim, Dong Wook
    • 한국의학물리학회지:의학물리
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    • 제29권4호
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    • pp.123-136
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    • 2018
  • The complex dose distribution and dose transfer characteristics of intensity-modulated radiotherapy increase the importance of precise beam data measurement and review in the acceptance inspection and preparation stages. In this study, we propose a process map for the introduction and installation of high-precision radiotherapy devices and present items and guidelines for risk management at the acceptance test procedure (ATP) and commissioning stages. Based on the ATP of the Varian and Elekta linear accelerators, the ATP items were checked step by step and compared with the quality assurance (QA) test items of the AAPM TG-142 described for the medical accelerator QA. Based on the commissioning procedure, dose quality control protocol, and mechanical quality control protocol presented at international conferences, step-by-step check items and commissioning guidelines were derived. The risk management items at each stage were (1) 21 ionization chamber performance test items and 9 electrometer, cable, and connector inspection items related to the dosimetry system; (2) 34 mechanical and dose-checking items during ATP, 22 multileaf collimator (MLC) items, and 36 imaging system items; and (3) 28 items in the measurement preparation stage and 32 items in the measurement stage after commissioning. Because the items presented in these guidelines are limited in terms of special treatment, items and practitioners can be modified to reflect the clinical needs of the institution. During the system installation, it is recommended that at least two clinically qualified medical physicists (CQMP) perform a double check in compliance with the two-person rule. We expect that this result will be useful as a radiation safety management tool that can prevent radiation accidents at each stage during the introduction of radiotherapy and the system installation process.