• 제목/요약/키워드: Equivalent Dose

검색결과 528건 처리시간 0.026초

파노라마 촬영시의 두경부 주요기관의 등가선량, 유효선량 및 위험도 (EQUIVALENT DOSE, EFFECTIVE DOSE AND RISK ASSESSMENT FROM PANORAMIC RADIOGRAPHY TO THE CRITICAL ORGANS OF HEAD AND NECK REGION)

  • 조봉혜;나경수;이애련
    • 치과방사선
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    • 제25권2호
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    • pp.437-445
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    • 1995
  • The purpose of this study was to evaluate the equivalent and effective dose, and estimate radiation risk to the critical organs of head and neck region from the use of adult and child mode in panoramic radiography. The results were as follows. 1. The salivary glands showed the highest equivalent and effective dose in adult and child mode. the equivalent and effective dose in adult mode were 837μSv and 20.93μSv, those in child mode were 462μSv and 11.54μSv, respectively. 2. Total effective doses to the critical head and neck organs were estimated 34.21μSv in adult mode, 20.14μSv in child mode. From these datas, the probabilities of stochastic effect from adult and child mode were 2.50x10/sup -6/ and 1.47x10/sup -6/. 3. The other remainder showed the greatest risk of fatal cancer. The risk estimate were 4.5 and 2.7 fatal malignancies in adult and child mode from million panoramic examinations. The bone marrow and thyroid gland showed about 0.1 fatal cancer in adult and child mode from these examinations.

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COMPUTATIONAL DETERMINATION OF NEUTRON DOSE EQUIVALENT LEVEL AT THE MAZE ENTRANCE OF A MEDICAL ACCELERATOR FACILITY

  • Kim, Hong-Suk;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • 제32권1호
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    • pp.15-20
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    • 2007
  • An empirical formula fur the neutron dose equivalent at the maze entrance of medical accelerator treatment rooms was derived on the basis of a Monte Carlo simulation. The simulated neutron dose equivalents around the Varian medical accelerator by the MCNPX code were employed. Two cases of target rotational planes were considered: parallel and perpendicular to maze walls. Most of the maximum neutron dose equivalents at the doorway were found when the target rotational planes were parallel to maze walls and the beams were directed to the inner maze entrances. The neutron dose equivalents at the outer maze entrances were calculated for about 698 medical accelerator facilities which were generated from the geometry configurations of running treatment rooms, based on such gantry rotation that produces the maximum neutron dose at the doorway. The results calculated with the empirical formula in this study were compared with those calculated by the Kersey method for 7 operating facilities. It was found that the maximum disagreement between the calculation of this study and that of the Kersey method was a factor of 8.54 with the value calculated by the Kersey method exceeding that of this study. It was concluded that the kersey method estimated the neutron dose equivalent at the doorway computed by MCNPX more conservatively than this study technique.

Average and Effective Energies, and Fluence-Dose Equivalent Conversion Factors for $^{239}Pu-Be,\;^{241}Am-Li\;and\;^{241}Am-F$ Neutron Sources

  • Ro, Seung-Gy;Yoo, Young-Soo
    • Nuclear Engineering and Technology
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    • 제3권3호
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    • pp.155-160
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    • 1971
  • 중성자 검출기의 교정을 위한 기초자료를 제공할 목적으로 당 연구실에서 보유하고 있는 $^{239}$ Pu-Be, $^{241}$Am-Li 및 241Am-F 중성자선원에 대한 평균 및 유효에너지와 중성자당 등가선량 환산인자를 계산하였다. 이들은 중성자 스펙트럼 및 중성자의 에너지 함수로서 주어진 등가선량에 대한 여러 보고 자료에 따라 수치계산법을 도입하여 구해졌다. 그 계산결과는 $^{239}$ Pu-Be, $^{241}$Am-Li 및 $^{241}$Am-F 순서로 각각 다음과 같이 주어진다 1. 평균에너지 4.07$\pm$0.33, 0.42 및 1.41 MeV; 2. 중성자의 단일충돌과정에 의하여 인체가 받게되는 선량의 개념에 따라 구한 유효에너지 4.45$\pm$0.344, 0.51 및 1.47 MeV; 3. 중성자의 다중충돌과정에 의하여 인체가 받게되는 선량의 개념에 따라 구한 유효에너지 4.50$\pm$0.36, 0.50 및 1.45 MeV; 4. 중성자당 단일충돌 등가선량 환산인자 (2.74$\pm$0.07)$10^{-8}$ , 1.58$\times$ $10^{-8}$ 및 2.34$\times$$10^{-8}$ rems/(n/$\textrm{cm}^2$); 5. 중성자당 다중충돌 등가선량 환산인자 (3.55$\pm$0.09)$10^{-8}$ , 2.19$\times$$10^{-8}$ 및 2.82$\times$$10^{-8}$ rems/(n/$\textrm{cm}^2$).

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300 keV 중성자(中性子)에 대한 방사선량(放射線量) 관계량(關係量)의 산정(算定) (Dosimetric Quantities for 300 keV Neutrons)

  • 이수용
    • Journal of Radiation Protection and Research
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    • 제11권1호
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    • pp.37-43
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    • 1986
  • ICRU 구(球)를 피사체(被射體)로 하여 300 keV 중성자(中性子)의 방사선량(放射線量) 관계량(關係量)을 평가(評價)하였다. 피사체내(被射體內)의 선량당량(線量當量) 분포(分布)를 직접(直接) 산정(算定)하기 위해 중성자(中性子)-광자(光子)-하전입자(荷電粒子) 결합수송(結合輸送)을 다룰 수 있는 몬테칼로 코드 NEDEP을 사용하였다. 계산결과(計算結果) 얻은 방사선량(放射線量) 관계량(關係量)은 다음과 같다. 심부선량당량지수(深部線量當量指數) $H_{I,d}:1.78{\times}10^{11}\;Sv-cm^2$ 표층선량당량지수(表層線量當量指數) $H_{I,s}:2.08{\times}10^{-1}\;Sv-cm^2$ 주위선량당량(周圍線量當量) $H^*(0.07):1.70{\times}10^{-11}\;Sv-cm^2$ 주위선량당량(周圍線量當量) $H^*(10):1.78{\times}10^{-11}\;Sv-cm^2$ 실효선질계수(實效線質係數) $\bar{Q}^*(10):12.4$

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이동형 방사선 차폐장치의 성능평가에 관한 연구 (A Study on the Performance Evaluation of Portable Radiation Shielding Apparatus)

  • 구본열;한상현
    • 대한방사선기술학회지:방사선기술과학
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    • 제41권4호
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    • pp.289-295
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    • 2018
  • When using a mobile X-ray unit, primary radiation creates medical images and secondary radiation scatters in many directions, which reduces image quality and causes exposure to patients, care givers and medical personnel. The purpose of this study was to develop a radiation shielding system for effectively shielding secondary radiation and evaluate its effectiveness. Using a mobile X-ray unit, spatial dose according to presence of human equivalent phantom and spatial dose using the developed shielding device were measured, and the phantom at 80 cm equidistance from center of X-ray was compared with spatial dose according to use of a shield. Measurements were taken at intervals of 10 cm every $30^{\circ}$ from the head direction($-90^{\circ}$) to the body direction($+90^{\circ}$). In the spatial dose measurement with and without the phantom, when the human equivalent Phantom was used, the spatial dose was increased by 40% in all directions from 40 cm to 100 cm from the central X-ray, and about 88% of the space dose was reduced when using the developed shields with the phantom. The equidistance dose at 80 cm from the central X-ray was increased by 39% from $5.1{\pm}0.26{\mu}Gy$ to $7.1{\pm}0.15{\mu}Gy$ when the human equivalent phantom was used, and when phantom was used and shielding was used, the spatial dose was reduced by about 90% from $7.1{\pm}0.15{\mu}Gy$ to $0.7{\pm}0.07{\mu}Gy$. The spatial dose of natural radiation was measured to be about $0.2{\pm}0.04{\mu}Gy$ when using the developed shielding with Phantom at a distance of 1 m or more. It is expected that by using the developed shielding system, it will be possible to effectively reduce secondary radiation dose received in all directions and to ensure safe imaging.

콘크리트 공동주택과 근린생활 시설의 환경방사선에 관한 연구 (A Study on the Environmental Radiation of Concrete Apartments and Neighborhood Living Facilities)

  • 지태정;곽병준;민병인
    • 한국안전학회지
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    • 제24권2호
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    • pp.100-104
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    • 2009
  • In this study, the space gamma dose rates in the apartments structured with concrete were measured in accordance with construction year. In addition, the environmental radiation rates coming from the subway platforms and the road tunnels were analyzed in the equivalent dose by multiplying the absorbed dose with the radiation weighting factors. The space gamma dose rates measured in apartments were higher than those of outdoor which was $0.08{\sim}0.11uSv/h$ in the natural conditions. Especially, the older construction year is, the higher becomes space gamma dose rate. The average gamma dose rates in the subway platforms were measured. In the case of Busan and Daegu subway, the earlier the opening year is, the higher becomes dose rate. However, the dose rates of Seoul subway Lines were high overall, regardless of opening year. Seoul subway Line 6 showed the highest value of 0.21uSv/h. The gamma dose rate in road tunnels was higher than one of the outdoor and increased with opening year like as apartment. In dose rate comparison of the concrete structures with the outdoor, therefore, the space gamma dose rate of indoor is higher than one of the outdoor and the older structures have a higher dose rate.

MCNPX를 이용한 방사선 치료실의 광중성자 선량 평가 (Evaluation of Photoneutron Dose in Radiotherapy Room Using MCNPX)

  • 박은태
    • 한국콘텐츠학회논문지
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    • 제15권6호
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    • pp.283-289
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    • 2015
  • 현재 방사선치료는 치료효과를 높이기 위해 고에너지 광자선의 사용이 증가하고 있는 추세이다. 일반적으로 6~8 MeV 이상의 고에너지 광자선을 사용하는 경우에는, 광핵반응에 의한 광중성자가 발생됨으로써 방사선 방호의 측면에서 많은 문제를 야기 시킬 수 있다. 이에 본 연구는 MCNPX를 이용하여 방사선 치료실의 광중성자 선량분포를 분석하였다. 그 결과 10 MV와 12 MV 구간에서 급격한 흡수선량의 증가를 보였다. 이를 통해 10 MV를 시작으로 광중성자 플루언스의 급격한 증가가 흡수선량으로 연계됨을 알 수 있었다. 또한 산출된 흡수선량을 바탕으로 등가선량을 환산한 결과는 ICRP 103 권고안의 경우, 낮은 에너지 범위에서 인체의 흡수선량에 대한 2차 광자의 기여를 반영함으로써 ICRP 60 권고안에 비해 낮은 등가선량을 나타냈다.

한약의 안전성 등급화를 위한 evidence-based approach : Human equivalent dose-based the margin of safety (Evidence-based approach for herbal medicine-safety classification : Human equivalent dose-based the margin of safety)

  • 박영철;이선동
    • 대한예방한의학회지
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    • 제17권3호
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    • pp.19-30
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    • 2013
  • This study was aimed to develop a new formula for herbal medicine-safety classification in terms of evidence-based medicine. Recently, human equivalent dose(HED)-based therapeutic index was developed for herbal medicine-safety classification by transforming $LD_{50}$ to HED. However, the use of the $ED_{50}$ and $LD_{50}$ to derive the therapeutic index may be misleading as to safety, depending on the slope of the dose-response curves for therapeutic and lethal effects. To overcome this deficiency, HED-based MOS(Margin of Safety)was developed and suggested in this study. The HED-based MOS developed by using $LD_1$, changing to ALD(approximate lethal dose), and $ED_{99}$. The HED-based MOS seems to be more useful and safer than HED-based therapeutic index since its values for several herbal medicines are basically two times less than the values from HED-based therapeutic index. Thus, HED-based MOS can be a good example of Evidence-based approach for herbal medicine-safety classification.

방사선치료 관련 연구를 위한 선량 체적 히스토그램 분석 프로그램 개발 (A Dose Volume Histogram Analyzer Program for External Beam Radiotherapy)

  • 김진성;윤명근;박성용;신정석;신은혁;주상규;한영이;안용찬
    • Radiation Oncology Journal
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    • 제27권4호
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    • pp.240-248
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    • 2009
  • 목 적: 방사선치료 관련 연구를 수행함에 있어서 선량 체적 히스토그램(dose volume histogram, DVH)을 분석하는 것이 필수적이나 상용 방사선치료계획시스템에서 수행할 수 없다. 본 연구는 이러한 선량 체적 히스토그램의 정보를 쉽게 분석할 수 있도록 소프트웨어를 제작하였다. 대상 및 방법: 방사선치료계획 시스템에서 치료계획 후에 환자의 DVH 데이터를 텍스트로 저장하여 이를 이용해서 DVH 상에서의 필요한 특정 값들(Vx, Dx)을 지정하여 획득할 수 있도록 하였고, Niemierko의 generalized equivalent uniform dose (EUD), Lyman-Kutcher-Burman 모델을 이용한 normal tissue complication probability (NTCP) 및 방사선치료의 2차 암유발 위험도 인자인 organ equivalent dose (OED)를 계산하는 프로그램을 개발하였다. 결 과: 환자의 데이터를 가지고 실제 방사선치료계획 시스템 상에서의 Vx, Dx와 NTCP 비교를 통해 개발된 프로그램의 계산 알고리즘을 검증하였고 0.1% 내의 오차를 보였으며 EUD 및 OED도 성공적으로 계산되었다. 결 론: 선량 체적 히스토그램을 분석하는 프로그램을 개발하였으며 다양한 방사선치료 관련 연구에 활용할 수 있을 것으로 예상된다.

몬테칼로법을 위한 선량당량 산정법의 도출 (Derivation of a Monte Carlo Estimator for Dose Equivalent)

  • 이재기
    • Journal of Radiation Protection and Research
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    • 제10권2호
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    • pp.89-95
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    • 1985
  • 연속감속근사법(CSDA)과 감속평균선질계수를 이용하여 선량당량 정의에서의 본래의 LET분포 개념을 하전입자속 스펙트럼의 개념으로 변환함으로써 새로운 선량당량 산정법을 도출하였다. 이 산정법을 몬테칼로법에 적용함으로써 주어진 방사선장에 위치한 피사체 내에서의 선량당량을 직접적으로 간편하게 산출할 수 있다. 산정에 필요한 감속평균 선질계수는 중성자와 연조직과의 상호작용으로부터 발생될 수 있는 모든 하전입자에 대하여 10 MeV 이하의 에너지 범위에서 산출하여 제시하였다.

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