• Title/Summary/Keyword: 선량 교정

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Invivo Dosimetry for Mammography with and without Lead Apron Using the Glass Dosimeters (유방촬영술에서 유리선량계를 이용한 납치마의 선량차폐 효과 측정)

  • Yu, Su-Jeong;Lim, Sangwook;Ma, Sun Young;Seo, Sun-Youl;Kim, Young-Jae;Kang, Young-Nam;Keum, Ki Chang;Cho, Samju
    • Progress in Medical Physics
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    • v.26 no.2
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    • pp.93-98
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    • 2015
  • The purpose of this study is to see the usefulness of lead apron for critical organs near the breast under examining. For clinical experiment, 30 female volunteers who agreed to their participation in the experiments, were chosen and divided into two groups, 15 in group A and 15 in group B respectively. group A is to see whether each side of breast under mammography affects to other side glandular on the critical organs is same, because it is not allowed to scan the both breast for same person or to scan repeatedly. Group B is to see the effectiveness of lead apron during the mammography of right breast. Glass dosimeters were placed on the thyroid, the contralateral breast, and lower abdomen where near the breast during examining. The average glandular doses on the surface in mammography of the thyroid gland, the contralateral breast, the lower abdomen were 0.0692 mGy, 0.6790 mGy, and 0.0122 mGy, respectively, which was an extremely low level of glandular dose. In group B, as to the thyroid gland, average dose was decreased from 0.0922 mGy to 0.0158 mGy. The average dose of contralateral breast was decreased from 0.8575 mGy to 0.0286 mGy. The average doses of lower abdomen was decrease 0.0150 mGy to 0.0173 mGy. As to the lower abdomen, dose decreased from 0.0150 mGy before the use of an apron down to 0.0173 mGy after the use. As p-value was under 0.05, statistically significant difference was observed between the two groups. Wearing an apron can have the protective effects on the thyroid gland up to 20 times lower than not wearing one. Besides, it is also necessary to protect the other breast during the examination by wearing one.

Development of Preliminary Quality Assurance Software for $GafChromic^{(R)}$ EBT2 Film Dosimetry ($GafChromic^{(R)}$ EBT2 Film Dosimetry를 위한 품질 관리용 초기 프로그램 개발)

  • Park, Ji-Yeon;Lee, Jeong-Woo;Choi, Kyoung-Sik;Hong, Semie;Park, Byung-Moon;Bae, Yong-Ki;Jung, Won-Gyun;Suh, Tae-Suk
    • Progress in Medical Physics
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    • v.21 no.1
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    • pp.113-119
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    • 2010
  • Software for GafChromic EBT2 film dosimetry was developed in this study. The software provides film calibration functions based on color channels, which are categorized depending on the colors red, green, blue, and gray. Evaluations of the correction effects for light scattering of a flat-bed scanner and thickness differences of the active layer are available. Dosimetric results from EBT2 films can be compared with those from the treatment planning system ECLIPSE or the two-dimensional ionization chamber array MatriXX. Dose verification using EBT2 films is implemented by carrying out the following procedures: file import, noise filtering, background correction and active layer correction, dose calculation, and evaluation. The relative and absolute background corrections are selectively applied. The calibration results and fitting equation for the sensitometric curve are exported to files. After two different types of dose matrixes are aligned through the interpolation of spatial pixel spacing, interactive translation, and rotation, profiles and isodose curves are compared. In addition, the gamma index and gamma histogram are analyzed according to the determined criteria of distance-to-agreement and dose difference. The performance evaluations were achieved by dose verification in the $60^{\circ}$-enhanced dynamic wedged field and intensity-modulated (IM) beams for prostate cancer. All pass ratios for the two types of tests showed more than 99% in the evaluation, and a gamma histogram with 3 mm and 3% criteria was used. The software was developed for use in routine periodic quality assurance and complex IM beam verification. It can also be used as a dedicated radiochromic film software tool for analyzing dose distribution.

Measurement of Absorbed Dose at the Tissue Surface from a Plain $^{90}Sr+^{90}Y$ Beta Sources (조직 표면에서의 베타선 흡수선량 측정)

  • Hah, Suck-Ho;Kim, Jeong-Mook;Yook, Chong-Chul
    • Journal of Radiation Protection and Research
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    • v.16 no.2
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    • pp.17-26
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    • 1991
  • Beta ray $(^{90}Sr+^{90}Y)$ absorbed dose at tissue surface was measured from the distance of 30cm by use of extrapolation chamber. In the measurement, following factors were considered: effective area of collecting electrode, polarity effect, ion recombination and window attenuation. The measured absorbed dose rate at tissue surface was $1.493{\mu}Gy/sec$ with ${\pm}2.9%$.

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The Comparative Analysis of External Dose Reconstruction in EPID and Internal Dose Measurement Using Monte Carlo Simulation (몬테 카를로 전산모사를 통한 EPID의 외부적 선량 재구성과 내부 선량 계측과의 비교 및 분석)

  • Jung, Joo-Young;Yoon, Do-Kun;Suh, Tae-Suk
    • Progress in Medical Physics
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    • v.24 no.4
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    • pp.253-258
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    • 2013
  • The purpose of this study is to evaluate and analyze the relationship between the external radiation dose reconstruction which is transmitted from the patient who receives radiation treatment through electronic portal imaging device (EPID) and the internal dose derived from the Monte Carlo simulation. As a comparative analysis of the two cases, it is performed to provide a basic indicator for similar studies. The geometric information of the experiment and that of the radiation source were entered into Monte Carlo n-particle (MCNPX) which is the computer simulation tool and to derive the EPID images, a tally card in MCNPX was used for visualizing and the imaging of the dose information. We set to source to surface distance (SSD) 100 cm for internal measurement and EPID. And the water phantom was set to be 100 cm of the source to surface distance (SSD) for the internal measurement and EPID was set to 90 cm of SSD which is 10 cm below. The internal dose was collected from the water phantom by using mesh tally function in MCNPX, accumulated dose data was acquired by four-portal beam exposures. At the same time, after getting the dose which had been passed through water phantom, dose reconstruction was performed using back-projection method. In order to analyze about two cases, we compared the penetrated dose by calibration of itself with the absorbed one. We also evaluated the reconstructed dose using EPID and partially accumulated (overlapped) dose in water phantom by four-portal beam exposures. The sum dose data of two cases were calculated as each 3.4580 MeV/g (absorbed dose in water) and 3.4354 MeV/g (EPID reconstruction). The result of sum dose match from two cases shows good agreement with 0.6536% dose error.

The Development and It′s Characteristics of New Film Dosimetry Algorithm for Personal Dosimetry (개인피폭 선량 측정을 위한 필름 배지 선량계의 새로운 알고리즘 개발 및 특성)

  • 이병용;장혜숙;봉정균;권수일
    • Progress in Medical Physics
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    • v.6 no.2
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    • pp.35-40
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    • 1995
  • Purpose: We have developed new film dosimetry algorithm for personal dosimetry and examined its characteristics. Materials and methods: Agfagaevart personal monitoring 2/10 films are used. Films which are in the film badges filtered with Cu 0.3mm, plastic 1.5mm, Aluminum 0.6mm and tin 0.8mm, were exposed by standard dosimetry laboratory. Irradiated energy categories are ANSI N13.1l Category III, and IV. Manual type film precessor and X-rite film densitometor was used. Filtered densities to energy relations and does to transformed densities relations can be obtained ofter transformation of H&D curves to linear shape by polynomal fitting. Reults : Personal dose be determined within 25% error for category m and 15% for category IV. And we are able to evaluate the exposed energy. Conclusion : New algorithm developed in this study is good for personal dosimetry within 30% error range for catergory III and IV. It is expectd to be complete personal dosimetry algorithm with further study for categrory, I, Dand II V.

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영광 원자력발전소 원자로 건물내 중성자 스펙트럼 측정

  • 손중권;신상운;조찬희
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05b
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    • pp.594-599
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    • 1998
  • 출력 운전중 원자로 건물내의 중성자 에너지 스펙트럼의 분포를 살펴보기 위해 중성자 스펙트럼 측정을 수행하였다. 영광4흐기 원자로 건물내 100ft 상에서 4곳, 122ft 상에서 4곳, 144 ft 상에서 8곳을 Bonner Multisphere Spectrometer(BMS) 시스템을 이용하여 중성자 스펙트럼을 측정하였다. BMS는 Cf-252 선원으로 교정하였으며 측정된 데이터는 BUNKI 코드를 이용하여 unfolding 하여 에너지 스펙트럼을 얻었다 분석 결과 100 ft의 경우 평균 중성자 에너지는 0.100 ~ 1.954 MeV, Fluence는 4.913$\times$$10^2$ ~ 1.478$\times$$10^4$ n/$\textrm{cm}^2$, 선량율은 0.56 ~ 289.37 mrem/hr의 분포를, 122 ft의 경우 평균 중성자 에너지는 0.122 ~ 0.320 MeV, Fluence는 4.586$\times$$10^{0}$ ~ 7.743$\times$$10^3$ n$\textrm{cm}^2$, 선량율은 0.05 ~ 201.46 mrem/hr의 분포를, 144 ft의 경우 평균 중성자 에너지는 0.062 ~ 0.578 MeV, Fluence는 7.922$\times$$10^{0}$ ~ 1.703$\times$$10^2$ n/$\textrm{cm}^2$, 선량율은 0.10 ~ 45.58 mrem/hr의 분포를 보였다.

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두경부암의 6MV 광자선 치료 시 표면선량 증가를 위한 Spoiler의 유용성 평가

  • 이강혁;김원택;이화중;김대영
    • The Journal of Korean Society for Radiation Therapy
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    • v.14 no.1
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    • pp.41-47
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    • 2002
  • 1.목적 두경부암(head and neck Ca)과 쇄골상부(Supraclavicular)에 6MV 광자선으로 치료 시 치료부위(Target volume)가 피부에서 대략 $1^{\sim}2mm$정도 깊이에 위치할 경우, 6MV 광자선의 선량분포는 표면선량이 낮아서 치료에 적합하지 않기 때문에 Bolus와 같이 사용하지만 Skin Sparing(피부보호)효과의 손실로 피부의 손상이 발생할 수 있다. 이러한 이유로 피부의 보호와 치료 시 표면선량의 증가를 위해 Spoiler(산란판)를 제작하여 측정 후 그 특성을 이해하고 선량의 분포를 통하여 Bolus와 비교한 후에 Spoiler의 유용성에 대해 평가하고자 하였다. 2.방법 Siemens사 선형가속기(PRIMUS)의 6MV 광자선을 사용하여 Spoiler의 사용여부 및 Spoiler의 사용 시에는 조사면의 크기를 $5{\times}5,\;7{\times}7,\;10{\times}10,\;15{\times}15,\;20{\times}20cm^2$로 하고 Spoiler와 표면과의 거리는 6, 10, 15cm로 바꾸어 가면서 물팬톰(PTW. 독일)을 이용해 깊이와 측방에 따른 선량분포를 Markus 전리함(PTW. 독일)으로 측정하였으며 전리함의 방수를 위해 씌어진 방수 캡 때문에 표면선량을 별도의 고형 팬톰으로 측정하였다. 표면의 측정선량은 전리함의 측면 벽 등에 의한 선량 측정치의 증가 현상으로 과 반응을 보였으며 이를 교정하였다. 그리고 측정된 데이터를 치료계획 시스템(Pinnacle 6.0m)으로 비교, 분석하였다. 3.결과 Spoiler의 사용 시 3cm깊이 측정선량 백분율과 Spoiler를 사용하지 않은 해당 치료 조사면의 3cm깊이 선량의 백분율에 일치하도록 하여 가상의 치료 깊이인 2mm에서 측정값을 비교하여 본 결과 조사면 $5{\times}5,\;10{\times}10,\;20{\times}20cm^2$에서 OPEN시 62, 64, $70\%$, Bolus는 97, 97, $99\%$로 Spoiler의 사용 시 표면과의 거리가 6cm에서 82, 98, $103\%$, 10cm에는 72, 89, $101\%$, 15m에 65, 79, $96\%$로 나타났으며 표면에서의 측정값을 비교하여 본 결과 OPEN시 11, 17, $27\%$, Bolus는 84, 84, $86\%$, Spoiler의 사용 시 6cm에서 40, 71, $93\%$, 10cm에는 25, 50, $81\%$, 15cm에 18, 36, $67\%$를 나타내었다. 또한 3m깊이에서의 측방 선량분포에서 Spoiler의 거리변화(6, 10cm)는 심부선량의 변화에 영향을 주지 않는 것으로 확인할 수 있었다. 그리고 위의 실험측정치를 치료계획 시스템에 입력하여 선량분포를 확인한 결과 Spoiler를 사용하는 경우 OPEN에 비해 선량분포 영역을 표면으로 끌어 올릴 수 있으며 Bolus 보다 피부 보호효과는 어느 정도 유지가 되는 것을 보여주었다. 4.결론 이와 같이 Spoiler는 Bolus와 비교하여 6MV 광자선의 build up 영역을 표면으로 증가시키는 동시에 Skin Sparing(피부보호)효과를 유지할 수 있으며 두경부암의 치료에서 Spoiler의 사용이 가능한 조건으로는 조사면이 $5{\times}5cm^2$에서 Spoiler와 표면과의 거리가 6cm일 때, $7{\times}7cm^2$에서 6cm, 10cm였고 $10{\times}10cm^2$는 10cm, 15cm로, $15{\times}15cm^2$는 15cm의 간격으로 평가되었다. 또한 $20{\times}20cm^2$의 조사면, Spoiler가 6cm 간격 인 경우 Bolus를 사용한 것 보다 더욱 높은 표면선량을 나타내었다. 그러나 Spoiler와 표면간의 거리를 다르게 함으로써 깊이에 따라 선량분포를 다양하게 나타낼 수 있기 때문에 표면선량의 증가와 피부의 보호를 위해 환자의 피부 두께, 실제 치료 부위의 깊이 등을 고려한다면 Spoiler를 사용하는 것이 bolus를 사용하는 것보다 더 유용하게 적용할 수 있을 것으로 사료된다.

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Feasibility Study for Development of Transit Dosimetry Based Patient Dose Verification System Using the Glass Dosimeter (유리선량계를 이용한 투과선량 기반 환자선량 평가 시스템 개발을 위한 가능성 연구)

  • Jeong, Seonghoon;Yoon, Myonggeun;Kim, Dong Wook;Chung, Weon Kuu;Chung, Mijoo;Choi, Sang Hyoun
    • Progress in Medical Physics
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    • v.26 no.4
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    • pp.241-249
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    • 2015
  • As radiation therapy is one of three major cancer treatment methods, many cancer patients get radiation therapy. To exposure as much radiation to cancer while normal tissues near tumor get little radiation, medical physicists make a radiotherapy plan treatment and perform quality assurance before patient treatment. Despite these efforts, unintended medical accidents can occur by some errors. In order to solve the problem, patient internal dose reconstruction methods by measuring transit dose are suggested. As feasibility study for development of patient dose verification system, inverse square law, percentage depth dose and scatter factor are used to calculate dose in the water-equivalent homogeneous phantom. As a calibration results of ionization chamber and glass dosimeter to transit radiation, signals of glass dosimeter are 0.824 times at 6 MV and 0.736 times at 10 MV compared to dose measured by ionization chamber. Average scatter factor is 1.4 and Mayneord F factor was used to apply percentage depth dose data. When we verified the algorithm using the water-equivalent homogeneous phantom, maximum error was 1.65%.

High Energy Electron Dosimetry by Alanine/ESR Spectroscopy (Alanine/ESR Spectroscopy에 의한 고에너지 전자선의 선량측정)

  • Chu, Sung-Sil
    • Radiation Oncology Journal
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    • v.7 no.1
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    • pp.85-92
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    • 1989
  • Dosimerty based on electron spin resonance (ESR) analysis of radiation induced free radicals in amino acids is relevant to biological dosimetry applications. Alanine detectors are without walls and are tissue equivalent. Therefore, alanine ESR dosimetry looks promising for use in the therapy level. The dose range of the alanine/ESR dosimetry system can be extended down to 1 Gy. In water phantom the absorbed dose of electrons generated by a medical linear accelerator of different initial energies $(6\~21MeV)$ and therapeutic dose levels (1~60 Gy) was measured. Furthermore, depth dose measurements carried out with alanine dosimeters were compared with ionization chamber measurements. As the results, the measured absorbed doses for shallow depth of initial electron energies above 15 MeV were higher by$2\~5\%$ than those calculated by nominal energy $C_E$ factors. This seems to be caused by low energy scattered beams generated from the scattering foil and electron cones of beam projecting device in medical linear accelerator.

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Comparison Study of Experimental Neutron Room Scattering Corrections with Theoretical Corrections in RCL's Calibration Facility at KAERI (한국원자력연구소 중성자교정실에 대한 중성자산란보정인자 결정연구)

  • Yoon, Suk-Chul;Chang, Si-Young;Kim, Jong-Soo;Kim, Jang-Lyul;Kim, Bong-Hwan
    • Journal of Radiation Protection and Research
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    • v.22 no.1
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    • pp.29-33
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    • 1997
  • Neutron room scattering corrections that should be made when neutron detectors are calibrated with a $D_2O$ moderated $^{252}Cf$ neutron source in the center of a calibration room are considered. Such room scattering corrections are dependent on specific neutron source type, detector type, calibration distance, and calibration room configuration. Room scattering corrections for the responses of a thermoluminescence dosimeter and two different types of spherical detectors to neutron source in the Radiation Calibration Laboratory(RCL) neutron calibration facility at the Korea Atomic Energy Research Institute(KAERI) were experimentally determined and are presented. The measured room scattering results are then compared with theoretical results calculated by predicting room scattering effects in terms of parameters related to the specific configuration. Agreement between measured and calculated scattering correction is generally about 10% for three kinds of detectors in the calibration facility.

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