• 제목/요약/키워드: equivalent dose

검색결과 518건 처리시간 0.02초

History of the Photon Beam Dose Calculation Algorithm in Radiation Treatment Planning System

  • Kim, Dong Wook;Park, Kwangwoo;Kim, Hojin;Kim, Jinsung
    • 한국의학물리학회지:의학물리
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    • 제31권3호
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    • pp.54-62
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    • 2020
  • Dose calculation algorithms play an important role in radiation therapy and are even the basis for optimizing treatment plans, an important feature in the development of complex treatment technologies such as intensity-modulated radiation therapy. We reviewed the past and current status of dose calculation algorithms used in the treatment planning system for radiation therapy. The radiation-calculating dose calculation algorithm can be broadly classified into three main groups based on the mechanisms used: (1) factor-based, (2) model-based, and (3) principle-based. Factor-based algorithms are a type of empirical dose calculation that interpolates or extrapolates the dose in some basic measurements. Model-based algorithms, represented by the pencil beam convolution, analytical anisotropic, and collapse cone convolution algorithms, use a simplified physical process by using a convolution equation that convolutes the primary photon energy fluence with a kernel. Model-based algorithms allowing side scattering when beams are transmitted to the heterogeneous media provide more precise dose calculation results than correction-based algorithms. Principle-based algorithms, represented by Monte Carlo dose calculations, simulate all real physical processes involving beam particles during transportation; therefore, dose calculations are accurate but time consuming. For approximately 70 years, through the development of dose calculation algorithms and computing technology, the accuracy of dose calculation seems close to our clinical needs. Next-generation dose calculation algorithms are expected to include biologically equivalent doses or biologically effective doses, and doctors expect to be able to use them to improve the quality of treatment in the near future.

상한론(傷寒論)에서 치자(梔子)의 기원(基原)과 1일 복용량 (A Research on the origin and Daily Dose of Gardeniae Fructus in Shanghanlun)

  • 김인락
    • 대한본초학회지
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    • 제26권4호
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    • pp.155-161
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    • 2011
  • Objective : The purpose of this study is to determine the origin and daily dose of Gardeniae Fructus in Shanghanlun. Methods : Define the origin and daily dose of Gardeniae Fructus by searching Shanhanlun and Herbology Books(本草書). And Compared these with those of current Gardeniae Fructus. Results : According to Shanhanlun, the origin of Gardeniae Fructus is Gardenia jasminoides, but G. jasminoides f. longicarpa must excluded since originally it was used for dyeing. Among the 8 prescriptions containing Gardeniae Fructus, 15 Gardeniae Fructuses for the daliy dose in Chijabekpi-tang(Zhizibopi-tang) is assumed to be 14 Gardeniae Fructuses, as it is found 14 in many other prescriptions same in other prescriptions. The quantity of 14 Gardeniae Fructuses in Shananlun is 3 Ryang(兩), which is equal to 19.5 g in the current measurement. 1 Gardeniae Fructus is equal to 1.4 g. The length of the Gardeniae Fructus in the market which is produced in korea is 22-27 mm, and the diameter is 15-19 mm, whereas in China it is 20-25 mm, and the diameter is 13-18 mm. This meets the standard requirements of the Pharmacopoeia. Conclusions : As a result from above, the origin of Gardeniae Fructus is Gardenia jasminoides, but G. jasminoides f. longicarpa must be excluded. The recommended dose in a day is 14 Gardeniae Fructuses, which is equivalent to 19.5 g, the amount generally used in Shanhanlun.

조직 등가 섬광체를 이용한 계수형 선량계의 개발과 특성 평가 (Development and Characterization of a Dosimeter Using Tissue-Equivalent Scintillator by Photon-Counting Method)

  • 천종규;김성환;김홍주
    • 센서학회지
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    • 제23권1호
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    • pp.29-34
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    • 2014
  • A dosimeter using tissue-equivalent scintillator by photon-counting method was developed and evaluated in its performance. The dosimeter is portable and can be operated by low power from lap-top computer. A data-acquisition software of the dosimeter system was developed by Labwindows/CVI based on Windows. The energy to channel ratio for energy calibration was 0.839 keV/ch. obtained from pulse height spectrum of $^{137}Cs$ and $^{60}Co$ gamma-ray. Using the dosimeter system, the absorbed dose of environmental radiation in Gyungju was 0.18 ${\mu}Sv/h$.

Reduction of Outdoor and Indoor Ambient Dose Equivalent after Decontamination in the Fukushima Evacuation Zones

  • Yoshida-Ohuchi, Hiroko;Kanagami, Takashi;Naitoh, Yutaka;Kameyama, Mizuki;Hosoda, Masahiro
    • Journal of Radiation Protection and Research
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    • 제42권1호
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    • pp.42-47
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    • 2017
  • Background: One of the most urgent issues following the accident at the Fukushima Daiichi nuclear power plant (FDNPP) was the remediation of the land, in particular, for residential area contaminated by the radioactive materials discharged. In this study, the effect of decontamination on reduction of ambient dose equivalent outdoors and indoors was evaluated. The latter is essential for residents as most individuals spend a large portion of their time indoors. Materials and Methods: From December 2012 to November 2014, thirty-seven Japanese single-family detached wooden houses were investigated before and after decontamination in evacuation zones. Outdoor and indoor dose measurements (n = 84 and 114, respectively) were collected based on in situ measurements using the NaI (Tl) scintillation surveymeter. Results and Discussion: The outdoor ambient dose equivalents [$H^*(10)_{out}$] ranged from 0.61 to $3.71{\mu}Sv\;h^{-1}$ and from 0.23 to $1.32{\mu}Sv\;h^{-1}$ before and after decontamination, respectively. The indoor ambient dose equivalents [$H^*(10)_{in}$] ranged from 0.29 to $2.53{\mu}Sv\;h^{-1}$ and from 0.16 to $1.22{\mu}Sv\;h^{-1}$ before and after decontamination, respectively. The values of reduction efficiency (RE), defined as the ratio by which the radiation dose has been reduced via decontamination, were evaluated as $0.47{\pm}0.13$, $0.51{\pm}0.13$, and $0.58{\pm}0.08$ ($average{\pm}{\sigma}$) when $H^*(10)_{out}$ < $1.0{\mu}Sv\;h^{-1}$, $1.0{\mu}Sv\;h^{-1}$ < $H^*(10)_{out}$ < $2.0{\mu}Sv\;h^{-1}$, and $2.0{\mu}Sv\;h^{-1}$ < $H^*(10)_{out}$, respectively, indicating the values of RE increased as $H^*(10)_{out}$ increased. It was found that the values of RE were $0.53{\pm}0.12$ outdoors and $0.41{\pm}0.09$ indoors, respectively, indicating RE was larger outdoors than indoors. Conclusion: Indoor dose is essential as most individuals spend a large portion of their time indoors. The difference between outdoors and indoors should be considered carefully in order to estimate residents' exposure dose before their returning home.

MV X선의 방사선 선량 증강 현상에서 물리적 특성과 이차입자의 발생 (Characterization of Physical Processes and Secondary Particle Generation in Radiation Dose Enhancement for Megavoltage X-rays)

  • 황철환;김정훈
    • 한국방사선학회논문지
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    • 제13권5호
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    • pp.791-799
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    • 2019
  • 선량 증강 현상에서 발생하는 물리적 특성과 증강 물질과의 상호 작용으로부터 발생하는 이차입자 생성을 평가하였다. Geant 4, MIRD 두부 팬텀을 이용한 몬테카를로 전산 모사를 진행하였으며, 선형가속기에서 발생되는 4, 6, 10, 15, 18, 25 MV X선을 선원으로 적용하였다. 10, 20, 30 mg/g의 금(aurum), 가돌리늄(gadolinium) 증강 물질을 팬텀 내부 종양에 모사하였으며, 물리적 상호작용의 변화와 이차입자 발생에 따른 입자플루언스와 초기 에너지로부터 방사선가중인자를 고려하여 등가선량을 평가하였다. 방사선 선량 증강 물질에 의한 상호작용은 고 원자번호에서 기인하여 광전효과에 의한 에너지 흡수를 높이는 것으로 나타났으며, 10 MV 이상의 에너지에서는 광핵반응의 증가를 나타내었다. 이로 인해, 팬텀 내부에서 양성자, 중성자와 같은 이차입자 발생의 증가를 보였으며, 중성자에 의한 등가선량이 최대 424.2배 증가하는 것으로 나타났다. 본 연구는 선량 증강 현상에서의 에너지 전달, 흡수의 물리적 과정을 모사하여, 증강 현상에서 발생하는 물리적 특성을 분석하고자 하였다. 이러한 결과는 향후 in-vivo, in-vitro 선량 증강 실험을 위한 기초 자료로 활용될 수 있을 것으로 사료된다.

Feasibility of normal tissue dose reduction in radiotherapy using low strength magnetic field

  • Jung, Nuri Hyun;Shin, Youngseob;Jung, In-Hye;Kwak, Jungwon
    • Radiation Oncology Journal
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    • 제33권3호
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    • pp.226-232
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    • 2015
  • Purpose: Toxicity of mucosa is one of the major concerns of radiotherapy (RT), when a target tumor is located near a mucosal lined organ. Energy of photon RT is transferred primarily by secondary electrons. If these secondary electrons could be removed in an internal cavity of mucosal lined organ, the mucosa will be spared without compromising the target tumor dose. The purpose of this study was to present a RT dose reduction in near target inner-surface (NTIS) of internal cavity, using Lorentz force of magnetic field. Materials and Methods: Tissue equivalent phantoms, composed with a cylinder shaped internal cavity, and adjacent a target tumor part, were developed. The phantoms were irradiated using 6 MV photon beam, with or without 0.3 T of perpendicular magnetic field. Two experimental models were developed: single beam model (SBM) to analyze central axis dose distributions and multiple beam model (MBM) to simulate a clinical case of prostate cancer with rectum. RT dose of NTIS of internal cavity and target tumor area (TTA) were measured. Results: With magnetic field applied, bending effect of dose distribution was visualized. The depth dose distribution of SBM showed 28.1% dose reduction of NTIS and little difference in dose of TTA with magnetic field. In MBM, cross-sectional dose of NTIS was reduced by 33.1% with magnetic field, while TTA dose were the same, irrespective of magnetic field. Conclusion: RT dose of mucosal lined organ, located near treatment target, could be modulated by perpendicular magnetic field.

Pre-dose effect를 이용한 고고학 시료의 연대측정 (The age dating for an archaeological sample using pre-dose effect)

  • 김명진;홍덕균
    • 분석과학
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    • 제18권4호
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    • pp.329-337
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    • 2005
  • Pre-dose 연대측정법은 석영의 $110^{\circ}C$ TL 피크의 민감도가 매장 기간 동안 시료가 흡수한 pre-dose와 활성 온도까지의 열처리에 의해 변화되는 pre-dose 현상을 이용한 연대측정법이다. 이 연구에서는 서천 추동리 문화유적에서 채집된 후 화학적으로 분리된 석영시료를 대상으로 pre-dose 연대측정을 실시하였다. 자연축적선량 결정을 위하여 MA(Multiple Activation)법이 적용되었으며 활성온도는 시료의 민감도 변화를 고려하여 $500^{\circ}C$로 결정하였고 냉광(luminescence)의 합산은 $85-105^{\circ}C$ 영역에서 이루어졌다. 최종적으로 산출된 시료의 연대는 $1725{\pm}25$년(1 ${\sigma}$ SD)이었으며 오차 범위 내에서 방사성탄소 연대측정 결과와 정확히 일치하고 radiocarbon plateau에 포함된 방사성탄소 연대측정보다 높은 정밀도를 가짐을 알 수 있었다. 결론적으로 pre-dose 연대측정을 통하여 산출된 연대는 정밀도와 정확도의 높은 증가로 인하여 기원 이후의 고고학적 사건들에 대한 지시자로서의 역할이 가능하리라 기대된다.

Neutron Dosimetry and Monitoring in the Radiation Environment

  • Nakamura, Takashi
    • Journal of Radiation Protection and Research
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    • 제14권2호
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    • pp.51-62
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    • 1989
  • The high efficiency moderated-type neutron spectrometer and doseequivalent counter were developed for the measurement of low level environmental neutrons. By using these detectors, the neutron energy spectra and dose equivalent rates due to skyshine effect were measured in the environment surrounding the accelerator facilities and also the altitude variation of cosmic ray neutrons in the aircraft flying over Japan.

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고(高) 에너지 전자선(電子線) 치료시(治療時) 체내(體內) 공동(空洞)으로 인(因)한 선량분포(線量分布)의 변동(變動) (Perturbation of Dose Distributions for Air Cavities in Tissue by High Energy Electron)

  • 추성실;이도행;최병숙
    • Journal of Radiation Protection and Research
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    • 제1권1호
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    • pp.22-30
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    • 1976
  • The perturbation of dose distribution adjacent to cavities in high energy electron has shown that the percentage of dose increase varies markedly as a function of the build-up layer, the length and thickness of the cavities, and the electron energy. The dose distribution showed that cavities similar in size to those encountered in the head and neck measured by industrial film dosimetry and corrected by ionization chambers. The most increased doses by measuring are resulted in a localized dose of up to 130% of that measured at the depth of maximum dose within a homogeneous tissue equivalent phantom. The measured values and correction factors of dose perturbation due to air cavities showed in diagrams and would be summarized as follows. 1. In $8{\sim}12MeV$ electron beams, the most marked dose is observed when the build-up layer thickness is 0.5cm and cavity volume is $2{\times}2{\times}2cm^3$. 2. The highest dose point is located under cavity when the energy is increased and cavity length is longer. 3. The cavity length at which the maximum percentage dose occurs decreases with increasing energy. 4. The highest percentage cavity doses are obtained when the energy is high, the build-up layer is thin, the thickness of the cavity is large, and the length of the cavity is approximately 1 to 3cm. 5. The doses of upper portion of cavity are less than the standard dose distribution as 5 to 10%. 6. The maximum range of electron beam are extended as much as thickness of cavity. 7. A cavity having a length of 5cm closely approximates a cavity of infinite length.

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