• Title/Summary/Keyword: 흡수선량 평가

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Personnel Dosimetry Performance Test (개인방사선 피폭선량판독 성능시험)

  • Na, Seong-Ho;Han, Seung-Jae;Lee, Dew-Hey;Cho, Dae-Hyung
    • Journal of Radiation Protection and Research
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    • v.21 no.2
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    • pp.131-138
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    • 1996
  • This paper describes the methods and results of the personnel dosimetry performance tests which were been implemented for the first time in Korea in 1995. Seven categories, except the neutron category prescribed in the ANSI N13.11-1993, were adopted in the test. Fifteen types of dosimeters were participated by fourteen dosimeter processing institutes. A total of 129 dosimeters were selected to test-each type - 15 dosimeters for each of the seven categories and 24 for the controls. A total of 144 radiation categories were employed in the test and a total of 2560 (including 400 controls)dosimeters were submitted-7 categories for each type of the fifteen types dosimeters and 39 categories for the retest. The performance index in each category. sum of the absolute value of the bias and the standard deviation value of the performance quotient. was estimated by the use of delivered and processed dose equivalents according to the standard procedure. The performance in a given category was assessed as acceptable, for the deep and shallow dose equivalents (or the absorbed dose), if the performance index was less than 0.5. The test results showed 54% of the processors passed in the first test, 33% in the retest and 13% in the second retest.

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Research on Dose Reduction During Computed Tomography Scanning by CARE kV System and Bismuth (전산화 단층검사 시 Bismuth와 CARE kV System을 이용한 선량 저감화에 대한 연구)

  • Kwak, Yeong-Gon;Kim, Chong-Yeal;Jeong, Seong-Pyo
    • The Journal of the Korea Contents Association
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    • v.14 no.8
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    • pp.233-242
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    • 2014
  • The purpose of this study is to compare the reduction of the dose radioactivity by CARE kV with that of the Bismuth shielding. First, CT was performed with transparent materials, including a Bismuth shielder which is a well-known material for decreasing the dose of radiation. Moreover, we have estimated and compared the affects of the reduction of dose on eye lens, thyroid, breast and genitals. These steps aim to compare reactions with and without the application of the Rando phantom with PLD as well as with CARE kV or not. As a result, during the Brain angio scan, the dose of CARE kV set inspection test methods showed the least dose. Depending on whether we use CARE kV, which showed the effect of dose reduction by 63%. During the Carotid angio scan, the dose was increased by 13% by how to set CARE kV+Bismuth. During the Cardiac angio scan, which showed the effect of dose reduction by 31% by how to set CARE kV+Bismuth. During the Lower extremity angio scan, the dose was measured least by how to set up the whole Bismuth. Compared with CARE kV set of test methods, which showed the effect of dose reduction by 9%.

Improvement on the KFOOD Code for More Realistic Assessment of the Annual Food Chain Radiation Dose Due to Operating Nuclear Facilities (가동중 원자력 시설에 의한 년간 섭식경로 피폭선량 평가의 현실성 제고를 위한 KFOOD 코드의 개선)

  • Park, Yong-Ho;Lee, Chang-Woo;Kim, Jin-Kyu;Lee, Myung-Ho;Lee, Jeong-Ho
    • Nuclear Engineering and Technology
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    • v.25 no.3
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    • pp.437-446
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    • 1993
  • More realistic calculation models for evaluating man's annual intakes of radionuclides released from operating nuclear facilities were established. For the application of these models, the harvest years of food and feed crops consumed in the year of dose assessment and every year's average concentrations of a radionuclide in air and in water for the whole period of real operation had to be taken into account. KFOOD, an existing equilibrium food chain computer code for the Korean dose assessment, was modified according to the models. Sample runs of the modified code on the assumption of a constant release during 10 years' operation were made with three kinds of the input data files enabling the dose assessment in the improved method, the KFOOD method and another existing method, respectively, and the results were compared. Annual committed effective doses to Korean adult by intakes of Mn-54, Co-60, Sr-90, I-131 and Cs-137 calculated in the improved method were about 11, 2, 5, 60 and 3%, respectively, lower than the corresponding KFOOD dose. To the intakes of the radionuclides except Sr-90 evaluated in the improved method, foliar uptake contributed much more than root uptake did but, in the case of Sr-90, the result was opposite.

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Genotoxicity evaluation of balanced nutritional food for patients pasteurized by gamma irradiation at 4 kGy (4 kGy로 감마선 살균처리된 환자용 균형영양식의 유전독성 평가)

  • Song, Beom-Seok;Park, Jong-Heum;Kim, Jae-Kyung;Park, Ha-Young;Kim, Dong-Ho;Hong, Seong-Gil;Jeong, Sang-Hee
    • Food Science and Preservation
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    • v.24 no.1
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    • pp.100-106
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    • 2017
  • This study was conducted to evaluate the genotoxicity of balanced nutritional formular for patients containing various ingredients after gamma irradiation at 4 kGy. Since viable bacteria were not observed within the detection limit of 1 log CFU/g, a dose of 4 kGy was appropriate for the pasteurization of the formular. In a bacterial reverse mutation assay, both hot water and methanol extracts of the formular exhibited dose-independent responses, which was similar to those obtained from that of the negative control (distilled water or dimethyl sulfoxide). In a chromosomal aberration test using lung fibroblast cells of Chinese hamster, the numbers of normal chromosomes were comparable to those observed in the negative control, regardless of the treatment dose and metabolic activation system. Furthermore, no significant increases in the frequency of micronucleated polychromatic erythrocytes were observed relative to the control, when mice were fed with the formular at doses up to 2,000 mg/kg body weight. Therefore, the balanced nutritional formular for patients did not exhibit genotoxicity when pasteurization by gamma irradiation at 4 kGy.

Construction of voxel head phantom and application to BNCT dose calculation (Voxel 머리팬텀 제작 및 붕소중성자포획요법 선량계산에의 응용)

  • Lee, Choon-Sik;Lee, Choon-Ik;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.26 no.2
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    • pp.93-99
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    • 2001
  • Voxel head phantom for overcoming the limitation of mathematical phantom in depleting anatomical details was constructed and example dose calculation for BNCT was performed. The repeated structure algorithm of the general purpose Monte Carlo code, MCNP4B was applied for yokel Monte Carlo calculation. Simple binary yokel phantom and combinatorial geometry phantom composed of two materials were constructed for validating the voxel Monte Carlo calculation system. The tomographic images of VHP man provided by NLM(National Library of Medicine) were segmented and indexed to construct yokel head phantom. Comparison of doses for broad parallel gamma and neutron beams in AP and PA directions showed decrease of brain dose due to the attenuation of neutron in eye balls in case of yokel head phantom. The spherical tumor volume with diameter, 5cm was defined in the center of brain for BNCT dose calculation in which accurate 3 dimensional dose calculation is essential. As a result of BNCT dose calculation for downward neutron beam of 10keV and 40keV, the tumor dose is about doubled when boron concentration ratio between the tumor to the normal tissue is $30{\mu}g/g$ to $3{\mu}g/g$. This study established the voxel Monte Carlo calculation system and suggested the feasibility of precise dose calculation in therapeutic radiology.

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Evaluation of the Effectiveness of 3D Printing Shielding Devices using Monte Carlo Simulation in Plain Radiography (일반영상 검사 시 몬테칼로 시뮬레이션을 이용한 3D 프린팅 차폐기구의 효용성 평가)

  • Cho, Yong In;Kim, Jung Hoon
    • Journal of the Korean Society of Radiology
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    • v.14 no.3
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    • pp.303-311
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    • 2020
  • Scattering-ray generated during plain radiography can cause secondary exposure to organs and tissues other than the target area. Currently, Shielding devices used to reduce radiation exposure are mostly used for radiation protection of workers, and radiation protection of patients is rarely performed. Therefore, this study intends to evaluate the organ dose by scattered-rays and the effectiveness 3D printing materials as a radiation shielding device during plain radiography through simulation. As a result, the absorbed dose for each organ at the time of examination showed a high effect due to the secondary scattering-ray as the distance from the source was close and the organ closer to the skin surface. The dose reduction effect due to the use of 3D printing shielding devices to protect this showed a higher shielding effect in the case of mixed printing materials compared to plastics.

Dose Evaluation of Three-Dimensional Small Animal Phantom with Film Dosimetry (필름계측을 이용한 3차원 소동물 팬텀의 선량평가)

  • Han, Su Chul;Park, Seungwoo
    • Journal of radiological science and technology
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    • v.40 no.1
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    • pp.87-92
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    • 2017
  • The weight of small animal dosimetry has been continuously increased in pre-clinical studies using radiation in small animals. In this study, three-dimensional(3D) small animal phantom was fabricated using 3D printer which has been continuously used and studied in the various fields. The absorbed dose of 3D animal phantom was evaluated by film dosimetry. Previously, the response of film was obtained from the materials used for production of 3D small animal phantom and compared with the bolus used as the tissue equivalent material in the radiotherapy. When irradiated with gamma rays from 0.5 Gy to 6 Gy, it was confirmed that there was a small difference of less than 1% except 0.5 Gy dose. And when small animal phantom was irradiated with 5 Gy, the difference between the irradiated dose and calculated dose from film was within 2%. Based on this study, it would be possible to increase the reliability of dose in pre-clinical studies using irradiation in small animals by evaluating dose of 3D small animal phantom.

Evaluation of Lung Dose Using Linac Photon Beam in Geant 4 Simulation (Geant4 Simulation에서 Linac 광자선을 이용한 폐 선량평가)

  • Jang, Eun-Sung;Lee, Hyo-Yeong
    • Journal of the Korean Society of Radiology
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    • v.12 no.4
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    • pp.443-450
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    • 2018
  • The Geant 4 simulated the linear accelerator (VARIAN CLINAC) based on the previously implemented BEAMnrC data, using the head structure of the linear accelerator. In the 10 MV photon flux, Geant4 was compared with the measured value of the percentage of the deep dose and the lateral dose of the water phantom. In order to apply the dose calculation to the body part, the actual patient's lung area was scanned at 5 mm intervals. Geant4 dose distributions were obtained by irradiating 10 MV photons at the irradiation field ($5{\times}5cm^2$) and SAD 100 cm of the water phantom. This result is difficult to measure the dose absorbed in the actual lung of the patient so the doses by the treatment planning system were compared. The deep dose curve measured by water phantom and the deep dose curve calculated by Geant4 were well within ${\pm}3%$ of most depths except the build-up area. However, at the 5 cm and 20 cm sites, 2.95% and 2.87% were somewhat higher in the calculation of the dose using Geant4. These two points were confirmed by the geometry file of Genat4, and it was found that the dose was increased because thoracic spine and sternum were located. In cone beam CT, the dose distribution error of the lungs was similar within 3%. Therefore, if the contour map of the dose can be directly expressed in the DICOM file when calculating the dose using Geant4, the clinical application of Geant4 will be used variously.

The Enhancement of Skin Sparing by Tray Materials for High Energy Photon Beam (고에너지 광자선치료에서 고정판 흡수물질을 이용한 피부보호효과의 향상)

  • Chu, Sung-Sil;Lee, Chang-Geol;Kim, Gwi-Eon
    • Radiation Oncology Journal
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    • v.11 no.2
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    • pp.449-454
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    • 1993
  • The skin sparing effect associated with high energy x-ray or gamma ray beams may be reduce or lost under certain conditions of treatment. Current trends in using large fields. Shield carrying trays, compensating filters, and isocentric methods of treatment have posed problems of increased skin dose which sometimes become a limiting factor in giving adquate tumor doses. We used the shallow ion chamber to measure the phantom surface dose and the physical treatment variables for Co-60 gamma ray, 4MV and 10 MV x-ray beam. The dependence of percent surface dose on field sizes, atomic number of the shielding tray materials and its distance from the surface for 4, 10MV x-rays and Co-60 gamma ray is qualitatively similar. The use of 2 mm thick tin filter is recommended for situations where a low atomic number tray is introduced into the beam at distances less than 15 cm from the surface and with the large field sized for 4 MV x-ray beam. In case of Co-60 gamma ray, the lead glass tray is suitable for enhancement of skin sparing. Also, the filter distance should be as large as possible to achieve substantial skin sparing.

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A Monte Carlo Study of Dose Enhancement with kilovoltage and megavoltage photons (몬테칼로 기법을 이용한 kV, MV X선에서의 선량증가 효과 비교 평가)

  • Hwang, ChulHwan;Im, In-Chul;Kim, Jung-Hoon
    • Journal of the Korean Society of Radiology
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    • v.11 no.2
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    • pp.87-94
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    • 2017
  • Monte Carlo simulations were used to assess dose enhancement effects for 60-, 90-, 120-, and 150-kV X-rays, and for 6- and 15-MV X-rays. The MCNPX code was used for a computer simulation of the ICRU slab phantom, and gold, gadolinium, and iron oxide (Fe2O3) were employed as dose enhancement agents. In consideration of the buildup region of the incident energy, agent concentrations of 5, 10, 15, and 20 mg/g were inserted on the surface of the phantom at a depth of 5 cm. Based on baseline values obtained in the absence of dose enhancement agents, a quantitative analysis was performed by evaluating depth-dependent changes in the absorbed energy and the dose enhancement factor (DEF). A higher concentration of dose enhancement agents led to a greater dose enhancement effect with iron oxide, gadolinium, and gold in descending order. For kilovoltage (kV) X-rays, as the incident energy was decreased and as the energy became closer to the ionization potential of the atoms in the enhancement agent, the dose enhancement effect increased. In the megavoltage (MV) X-ray range, dose enhancement was higher at 6 MV compared with 15 MV. However, the overall dose enhancements were significantly lower compared to the results obtained with kV X-rays.