• Title/Summary/Keyword: 선량계산

Search Result 722, Processing Time 0.029 seconds

Development of a Monte Carlo Simulation Code (CALEFF) for Calibrating Thyroid Internal Dose Measurement and Detection Efficiency Calculation (갑상선 내부피폭선량 측정치 보정을 위한 몬테카를로 모의실험 코드 (CALEFF) 개발 및 검출효율 계산)

  • Ahn, Ki-Soo;Cho1, Hyo-Sung
    • Journal of radiological science and technology
    • /
    • v.28 no.2
    • /
    • pp.117-122
    • /
    • 2005
  • According to the Para. 5 of Art 2 of the Korean Nuclear Safety Regulations, which was revised in 1999, internal dose assessment as well as external one should be performed by law for employees at a nuclear power plant from 2003, and their estimate errors should also be within 50%. Thus, more accurate internal dosimetry becomes important. Corresponding to such regulation revision, we are developing a more accurate thyroid-uptake internal dosimetric system and have developed a Monte Carlo simulation code, the so-called CALEFF, to calculate the detection efficiency of the dosimetric system. In this paper, we calculated detection efficiencies with various test conditions by using the CALEFF code and discussed their characteristics. We may use the detection efficiency calculated by the code in calibrating the thyroid internal dose from measured data.

  • PDF

Neutron Generation from a 24 MV Medical Linac (24 MV 의료용 선형가속기의 중성자 발생에 관한 연구)

  • Jeong Dong Hyeok;Kang Jeong Ku;Lee Jeong Ok
    • Progress in Medical Physics
    • /
    • v.16 no.2
    • /
    • pp.97-103
    • /
    • 2005
  • The energy spectra and dose calculations were performed for secondary neutrons from a 24 MV LINAC using MCNPX code (V2, 4, 0). The energy spectra for neutrons and photons emitted from the LINAC head, and absorbed dose to water were calculated in water phantom. The absorbed doses calculated with Monte Carlo were $0.66\~0.35$ mGy/photon Gy at the surface to d=5 cm, and calculated with interaction data was 0.52 mGy/photon Gy at the depth of electron equilibrium in water. We have shown that this work can be applied to dose estimation of neutrons from high energy LINAC through the comparison of our results with other results.

  • PDF

Calculation of the Air-Scattering Dose Rate by the Single Scattering Approximation (단일산란근사법(單一散亂近似法)에 의한 공기중(空氣中) 산란방사선량(散亂放射線量)의 계산(計算))

  • Yook, Chong-Chul;Ha, Chung-Woo;Lee, Jai-Ki;Moon, Philip S.
    • Journal of Radiation Protection and Research
    • /
    • v.4 no.1
    • /
    • pp.21-28
    • /
    • 1979
  • A calculation is presented of air-scattered gamma rays using the modified single-scattering approximation. The air-scattered tissue dose rates are calculated for a general purpose taking into account (a) the buildup and exponential attenuation, (b) the energy spectrum at the position of question and (c) the geometrical scattering volume in three dimensions. These calculations have been further modified to render them applicable to a typical field irradiation facility which is surrounded by a shield wall and in which the source is fitted with a beam collimating device. The results of the calculation include the energy spectra, angular distribution and tissue does rates at source-receiver separation distances of from 35m to 300m. The comparison shows that the present method developed may be generally adequate for the gamma-ray air-scattering problems in field irradiation facilities if energy and angular distribution at the shield are unimportant.

  • PDF

A Study of Usefulness for Megavoltage Computed Tomography on the Radiation Treatment Planning (메가볼트 에너지 전산화 단층 촬영을 이용한 치료계획의 유용성 연구)

  • Cho, Jeong-Hee;Kim, Joo-Ho;Khang, Hyun-Soo;Lee, Jong-Seok;Yoo, Beong-Gyu
    • Journal of radiological science and technology
    • /
    • v.33 no.4
    • /
    • pp.369-378
    • /
    • 2010
  • The purpose of this study was to investigate image differences between KVCT vs MVCT depending on a high densities metal included in the phantom and to analyze the r values for the purpose of the dose differences between each methods. We verified the possibilities for clinical indications that using MVCT is available for the radiation therapy treatment planning. Cheese phantom was used to get a density table for each CT and CT sinogram data was transferred to radiation planning computer through DICOM_RT. Using this data, the treatment dose plan has been calculated in RTP system. We compared the differences of r values between calculated and measured values, and then applied this data to the real patient's treatment planning. The contrast of MVCT image was superior to KVCT. In KVCT, each pixel which has more than 3.0 of density was difficult to be differentiated, but in MVCT, more than 5.0 density of pixels were distinguished clearly. With the normal phantom, the percentage of the case which has less than 1($r\leq1$, acceptable criteria) of gamma value, was 94.92% for KVCT and 93.87% for MVCT. But with the cheese phantom, which has high density plug, the percentage was 88.25% for KVCT and 93.77% for MVCT respectively. MVCT has many advantages than KVCT. Especially, when the patient has high density metal, such as total hip arthroplasty, MVCT is more efficient to define the anatomical structure around the high density implants without any artifacts. MVCT helps to calculate the treatment dose more accurately.

A Cosideration on Physical Aspects in Teleradiotherapy Chart QA (원격방사선치료 기록부의 QA 에서 물리적 측면의 고찰)

  • 강위생;허순녕
    • Progress in Medical Physics
    • /
    • v.10 no.2
    • /
    • pp.95-101
    • /
    • 1999
  • The aims of this report are to classify the incorrect data of patients and the errors of dose and dose distribution observed in QA activities on teleradiotherapy chart, and to analyze their frequency. In our department, radiation physicists check several sheets of patient chart to reduce numeric errors before starting radiation therapy and at least once a week, which include history, port diagram, MU calculation or treatment planning summary and daily treatment sheet. The observed errors are classified as followings. 1) Identity of patient, 2) Omitted or unrecorded history sheet even though not including the item related to dose, 3) Omission of port diagram, or omitted or erroneous data, 4) Erroneous calculation of MU and point dose, and important causes, 5) Loss of summary sheet of treatment planning, and erroneous data of patient in the sheet, 6) Erroneous record of radiation therapy, and errors of daily dose, port setup, MU and accumulated dose in the daily treatment sheet, 7) Errors leading inexact dose or dose distribution, errors not administerd even though its possibility, and simply recorded errors, 8) Omission of sign. Number of errors was counted rather than the number of patients. In radiotherapy chart QA from Jun 17, 1996 to Jul 31, 1999, no error of patient identity had been observed. 431 Errors in 399 patient charts had been observed and there were 405 physical errors, 9 cases of omitted or unrecorded history sheet, and 17 unsigned. There were 23 cases (5.7%) of omitted port diagram, 21 cases (5.2%) of omitted data and 73 cases (18.0 %) of erroneous data in port diagram, 13 cases (3.2 %) treated without MU calculation, 68 cases (16.3 %) of erroneous MU, 8 cases (2.0%) of erroneous point dose, 1 case (0.2 %) of omitted treatment planning summary, 11 cases (2.7%) of erroneous input of patient data, 13 cases (3.2%) of uncorrected record of treatment, 20 cases (4.9%) of discordant daily doses in MU calculation sheet and daily treatment sheet, 33 cases (8.1%) of erroneous setup, 52 cases (12.8%) of MU setting error, 61 cases (15.1%) of erroneous accumulated dose. Cases of error leading inexact dose or dose distribution were 239 (59.0 %), cases of error not administered even though its possibility were 142 (35.1 %), and cases of simply recorded error were 24 (5.9 %). The numeric errors observed in radiotherapy chart ranged over various items. Because errors observed can actually contribute to erroneous dose or dose distribution, or have the possibility to lead such errors, thorough QA activity in physical aspects of radiotherapy charts is required.

  • PDF

사용전 및 사용후 DUPIC 핵연료의 방사선량률 분석

  • 김윤구;박범락;임재용;박광헌;황주호
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1995.05b
    • /
    • pp.799-804
    • /
    • 1995
  • DUPIC 핵연료의 사용전 그리고 사용후 조건에서 방사선량을 분석하였다. 사용후 핵연료로 35,000 MWD/MTU의 표준 연소도와 50,000 MWD/MTU의 고 연소도을 사용하였고 선량률을 계산하기 위해 CANDU의 핵연료 집합체을 균등 혼합체로 가정 하였다. 조사선량율은 건식가공을 거치지 않았을 때 매우 높은 수치를 나타내었지만 건식가공을 한 후에는 많이 감소하개 됨 을 볼 수 있었다. 특히 Cs에 민감한 반응을 보였고 Cs을 100% 제거하였을 경우 전체 선량율이 약 90%가 줄어드는 결과를 얻었다. 아울러 사용후 DUPIC핵연료의 선량율도 건식가공 방법에 많은 영향을 받고 있다.

  • PDF

Evaluation of Electron Beam Dose Distribution by Age Diffusion Equation (연령 확산 이론에 의한 전자선의 조직내 선량분포 평가)

  • 추성실
    • Progress in Medical Physics
    • /
    • v.4 no.1
    • /
    • pp.29-39
    • /
    • 1993
  • Electron beams have found unique and complementary used in the treatment of cancer, but it's very difficult to delineate dose distribution, because of multi-collisions. Numerical solution is more usefull to describe electron distributed in tissue. A semi-empirical eqution is given for the dose at any point at various depths in water. This equation is a modificated model which was based on solutions of a general age diffusion equation. Parameters have been calulated from electron beams data with energies 6~18MeV form a LINAC for use in computerised dosimetry calculations. The depth doses and isodose curves are predicted as a function of the practical range, source skin distance and field size. Depth dose accuracy have been achieved 2% above 50% depth dose and 5% at lower doses, relative to maximum dose. Also, the shape of the isodose curves with the constrictions at higher dose and bulging ot lower values are accurately predicted. Computer calculated beams have been used to generate ever isodose distribution for certain clinical situations.

  • PDF

Development of the Reference Korean Female Voxel Phantom (한국인 기준여성 체적소형 모의체 개발)

  • Ham, Bo-Kyoung;Cho, Kun-Woo;Yeom, Yoen-Soo;Jeong, Jong-Hwi;Kim, Chan-Hyeong;Han, Min-Cheol
    • Journal of Radiation Protection and Research
    • /
    • v.37 no.1
    • /
    • pp.41-49
    • /
    • 2012
  • The objective of this study is for development of the reference Korean female phantom, HDRK-Woman. The phantom was constructed by adjusting a Korean woman voxel phantom to the Reference Korean data. The Korean woman phantom had been developed based on the high-resolution color slice images obtained from an adult Korean female cadaver. There were a total of 39 organs including the 27 organs specified in ICRP 103 for effective dose calculation. The voxel resolution of the phantom was $1.976{\times}1.976{\times}2.0619\;mm^3$ and the voxel array size is $261{\times}109{\times}825$ in the x, y and z directions. Then, the voxel resolution was changed to $2.0351{\times}2.0351{\times}2.0747\;mm^3$ for adjustment of the height and total bone mass of the phantom to the Reference Korean data. Finally, the internal organs and tissue were adjusted using in-house software program developed for 3D volume adjustment of the organs and tissue. The effective dose values of HDRK phantoms were calculated for broad parallel photon beams using MCNPX Monte Carlo code and compared with those of ICRP phantoms.