• 제목/요약/키워드: Absorbed Doses

검색결과 206건 처리시간 0.023초

The Accuracy of the Calculated Dose for a Cardiac Implantable Electronic Device

  • Sung, Jiwon;Son, Jaeman;Park, Jong Min;Kim, Jung-in;Choi, Chang Heon
    • 한국의학물리학회지:의학물리
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    • 제30권4호
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    • pp.150-154
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    • 2019
  • The objective of this study is to monitor the radiation doses delivered to a cardiac implantable electronic device (CIED) by comparing the absorbed doses calculated by a commercial treatment planning system (TPS) to those measured by an in vivo dosimeter. Accurate monitoring of the radiation absorbed by a CIED during radiotherapy is necessary to prevent damage to the device. We conducted this study on three patients, who had the CIED inserted and were to be treated with radiotherapy. Treatment plans were generated using the Eclipse system, with a progressive resolution photon optimizer algorithm and the Acuros XB dose calculation algorithm. Measurements were performed on the patients using optically stimulated luminescence detectors placed on the skin, near the CIED. The results showed that the calculated doses from the TPS were up to 5 times lower than the measured doses. Therefore, it is recommended that in vivo dosimetry be conducted during radiotherapy for CIED patients to prevent damage to the CIED.

Comparative Study of the Effective Dose from Panoramic Radiography in Dentistry Measured Using a Radiophotoluminescent Glass Dosimeter and an Optically Stimulated Luminescence Detector

  • Lee, Kyeong Hee;Kim, Myeong Seong;Kweon, Dae Cheol;Choi, Jiwon
    • Journal of the Korean Physical Society
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    • 제73권9호
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    • pp.1377-1384
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    • 2018
  • Accurate measurement of the absorbed dose and the effective dose is required in dental panoramic radiography involving relatively low energy with a rotational X-ray tube system using long exposures. To determine the effectiveness of measuring the irradiation by using passive dosimetry, we compared the entrance skin doses by using a radiophotoluminescent glass dosimeter (RPL) and an optically stimulated luminescence detector (OSL) in a phantom model consisting of nine and 31 transverse sections. The parameters of the panoramic device were set to 80 kV, 4 mA, and 12 s in the standard program mode. The X-ray spectrum was applied in the same manner as the panoramic dose by using the SpekCalc Software. The results indicated a mass attenuation coefficient of $0.008226cm^2/g$, and an effective energy of 34 keV. The equivalent dose between the RPL and the OSL was calculated based on a product of the absorbed doses. The density of the aluminum attenuators was $2.699g/cm^3$. During the panoramic examination, tissue absorption doses with regard to the RPL were a surface dose of $75.33{\mu}Gy$ and a depth dose of $71.77{\mu}Gy$, those with regard to the OSL were surface dose of $9.2{\mu}Gy$ a depth dose of $70.39{\mu}Gy$ and a mean dose of $74.79{\mu}Gy$. The effective dose based on the International Commission on Radiological Protection Publication 103 tissue weighting factor for the RPL were $0.742{\mu}Sv$, $8.9{\mu}Sv$, $2.96{\mu}Sv$ and those for the OSL were $0.754{\mu}Sv$, $9.05{\mu}Sv$, and $3.018{\mu}Sv$ in the parotid and sublingual glands, orbit, and thyroid gland, respectively. The RPL was more effective than the OSL for measuring the absorbed radiation dose in low-energy systems with a rotational X-ray tube.

이동형 구내 방사선촬영기로 촬영한 치근단 방사선사진의 흡수선량 및 유효선량 평가 (Absorbed and effective dose from periapical radiography by portable intraoral x-ray machine)

  • 조정연;한원정;김은경
    • Imaging Science in Dentistry
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    • 제37권3호
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    • pp.149-156
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    • 2007
  • Purpose: The purpose of this study was to measure the absorbed dose and to calculate the effective dose for periapical radiography done by portable intraoral x-ray machines. Materials and Methods: 14 full mouth, upper posterior and lower posterior periapical radiographs were taken by wall-type 1 and portable type 3 intraoral x-ray machines. Thermoluminescent dosemeters were placed at 23 sites at the layers of the tissue-equivalent ART woman phantom for dosimetry. Average tissue absorbed dose and radiation weighted dose were calculated for each major anatomical site. Effective dose was calculated using 2005 ICRP tissue weighted factors. Results: On 14 full mouth periapical radiographs, the effective dose for wall-type x-ray machine was 30 Sv; for portable x-ray machines were 30 Sv, 22 Sv, 36 Sv. On upper posterior radiograph, the effective dose for wall-type x-ray machine was 4 Sv; for portable x-ray machines doses were 4 Sv, 3 Sv, 5 Sv. On lower posterior radiograph, the effective dose for wall type x-ray machine was 5 Sv; for portable x-ray machines doses were 4 Sv, 4 Sv, 5 Sv. Conclusion: Effective doses for periapical radiographs performed by portable intraoral x-ray machines were similar to doses for periapical radiographs taken by wall type intraoral x-ray machines.

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Bias-corrected Hp(10)-to-Organ-Absorbed Dose Conversion Coefficients for the Epidemiological Study of Korean Radiation Workers

  • Jeong, Areum;Kwon, Tae-Eun;Lee, Wonho;Park, Sunhoo
    • Journal of Radiation Protection and Research
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    • 제47권3호
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    • pp.158-166
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    • 2022
  • Background: The effects of radiation on the health of radiation workers who are constantly susceptible to occupational exposure must be assessed based on an accurate and reliable reconstruction of organ-absorbed doses that can be calculated using personal dosimeter readings measured as Hp(10) and dose conversion coefficients. However, the data used in the dose reconstruction contain significant biases arising from the lack of reality and could result in an inaccurate measure of organ-absorbed doses. Therefore, this study quantified the biases involved in organ dose reconstruction and calculated the bias-corrected Hp(10)-to-organ-absorbed dose coefficients for the use in epidemiological studies of Korean radiation workers. Materials and Methods: Two major biases were considered: (a) the bias in Hp(10) arising from the difference between the dosimeter calibration geometry and the actual exposure geometry, and (b) the bias in air kerma-to-Hp(10) conversion coefficients resulting from geometric differences between the human body and slab phantom. The biases were quantified by implementing personal dosimeters on the slab and human phantoms coupled with a Monte Carlo method and considered to calculate the bias-corrected Hp(10)-to-organ-absorbed dose conversion coefficients. Results and Discussion: The bias in Hp(10) was significant for large incident angles and low energies (e.g., 0.32 for right lateral at 218 keV), whereas the bias in dose coefficients was significant for the posteroanterior (PA) geometry only (e.g., 0.79 at 218 keV). The bias-corrected Hp(10)-to-organ-absorbed dose conversion coefficients derived in this study were up to 3.09- fold greater than those from the International Commission on Radiological Protection publications without considering the biases. Conclusion: The obtained results will aid future studies in assessing the health effects of occupational exposure of Korean radiation workers. The bias-corrected dose coefficients of this study can be used to calculate organ doses for Korean radiation workers based on personal dose records.

흉부(胸部) X선검사시(線檢査時) 환자(患者)의 피폭선양(被曝線量)에 대(對)한 연구(硏究) (A Study of the Patient Dose in Chest Radiography)

  • 김창균
    • 대한방사선기술학회지:방사선기술과학
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    • 제13권1호
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    • pp.3-9
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    • 1990
  • A study was carried out to investigate the technical factors and the patient dose (entrance and absorbed dose) in chest P-A radiography based on the 86 hospitals in Seoul from July 1 to July 30, 1989. As a result of this study, main finding were as follow : 1. 51.2% of the surveyed hospitals made use of $60{\sim}69\;kVp$ as tube voltage in chest radiography 2. The majority of the surveyed(88.3%) have the use of $6{\sim}20\;mAs$ as tube current-time. 3. Percentage absorbed doses in patient were showed more than 90 percent in every tube voltage. 4. Object densities were all much the same in all tube voltages. 5. 48.8% of surveyed entrance doses ranged from $100\;{\mu}Sv$ to $190\;{mu}Sv$, and the mean dose was $158\;{\mu}Sv$.

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A SOLUTION TO THE PROBLEM WITH ABSORBED DOSE

  • Braby, Leslie A.
    • Nuclear Engineering and Technology
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    • 제40권7호
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    • pp.533-538
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    • 2008
  • In some situations, for example at very low doses, in microbeam irradiation experiments, or around high energy heavy ion tracks, use of the absorbed dose to describe the energy transferred to the irradiated target can be misleading. Since absorbed dose is the expected value of energy per mass it takes into account all of the targets which do not have any energy deposition. In many situations that results in numerical values, in Joules per kg, which are much less than the energy deposited in targets that have been crossed by a charged particle track. This can lead to confusion about the biochemical processes that lead to the consequences of irradiation. There are a few alternative approaches to describing radiation that avoid this potential confusion. Examples of specific situations that can lead to confusion are given. It is concluded that using the particle radiance spectrum and the exposure time, instead of absorbed dose, to describe these irradiations minimizes the potential for confusion about the actual nature of the energy deposition.

177Lu-EDTMP radiation absorbed dose evaluation in man based on biodistribution data in Wistar rats

  • Reza Bagheri
    • Nuclear Engineering and Technology
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    • 제55권1호
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    • pp.254-260
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    • 2023
  • Skeletal metastases are common in patients suffering from various primary cancers. Radiopharmaceuticals are an effective option for bone pain palliation. In this work, the radiation absorbed dose of 177Lu-EDTMP radiopharmaceutical was estimated for adult man based on biodistribution data in Wistar rats. The MIRD dose calculation method and the Sparks and Aydogan methodology were applied. The results shows that about 46% of injected activity is cumulated on the surface of the trabecular and cortical bones. Radiation absorbed doses of red bone marrow and osteogenic cells were estimated to about 1.1 and 6.2 mGy/MBq, respectively. The maximum administrated activity was obtained 27 MBq/kg of body weight with an effective dose of 0.23 mSv/MBq. The results were compared with other available data from literature. This study indicated that 177Lu-EDTMP provides therapeutic efficacy for achieving bone pain palliation with low undesired dose to other normal organs.

선형가속기형 방사선수술시 인형 팬텀에서 수정체 및 갑상선 선량 (Radiation Dose of Lens and Thyroid in Linac-based Radiosurgery in Humanoid Phantom)

  • 김대용;김일한
    • Radiation Oncology Journal
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    • 제16권4호
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    • pp.517-529
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    • 1998
  • 목적 : 정위방사선수술은 뇌동정맥기형 및 청신경초종, 뇌수막종양, 뇌하수체종양 뿐만 아니라 단일 전이성 종양의 치료에 있어서도 그 이용의 빈도가 급격히 늘어나는 추세이다. 그에 따라 목표부위에 있어서 정위방사선술의 선량분포에 관한 연구는 많이 발표되고 있으나 두 개강 외의 수정체 갑상선과 같이 방사선의 결정적 또는 확률적 효과에 민감한 장기와 같은 조직에서 흡수되는 선량에 관한 자료는 극히 제한적이다. 본 연구는 인체모형에서 방사선수술시 수정체 및 갑상선의 선량을 측정하고 그 선량에 영향을 미치는 변수를 규명하고자 하였다. 대상 및 방법 : 6 곳의 상이한 회전중심점에서 각각 서울대학교 의과대학 치료방사선과학교실에서 개발한 선형가속기형 정위방사선수술 기법을 이용하여 치료계획을 세웠다. 각 회전중심점당 6개의 arc를 기본으로 하고 각 arc의 범위는 100도를 기준으로 하고 보조콜리메이터 크기는 직경 2cm로 선정하였다. 각 arc 별로 250cGy 조사한 후 내회 열형광선량계를 이용하여 수정체 및 갑상선의 표면에 미치는 선량을 측정하였다. 결과 : 회전중심점 또는 arc plane 이 각 장기와 가까울수록 흡수 선량이 높았다. exit beam이 수정체나 갑상선을 지나지 않을 경우 각 장기의 선량은 최대선량의 0.23$\pm$0.08$\%$ 와 0.18$\pm$0.05$\%$ 이고, exit beam 이 수정체나 갑상선을 지나는 경우 각 장기의 선량은 최대선량의 0.76$\pm$0.12$\%$ 와 0.41$\pm$0.04$\%$ 이다. exit beam의 통과 여부가 각 장기의 선량에 미치는 가장 큰 인자이며, 장기를 통과하는 arc에 의해 흡수하는 선량은 총 선량의 80$\%$를 차지한다. 인체 모형의 표면선량과 5mm 깊이에서의 선량에 큰 차이가 없어 표면선량을 수정체 및 갑상선 선량으로 대체할 수 있다고 판단한다. 결론 : 정위방사선수술시 인체모형의 수정체와 갑상선에 흡수되는 방사선량을 측정한 결과 회전중심점 및 arc plane 이 각 장기와 가까울수록 높은 흡수 선량을 나타내었으며, exit beam이 수정체나 갑상선을 통과하는 경우 흡수선량이 높았고 exit beam의 통과 여부가 각 장기의 흡수선량에 가장 큰 영향을 미쳤다. 또한 수정체와 갑상선의 표면선량은 수정체 및 갑상선 선량과 큰 차이가 없었다. 최적의 방사선수술을 위한 계획을 수립할 경우 각 장기의 선량은 최대 1$\%$ 미만으로 후유증을 일으키기에 낮은 선량이기는 하나, 특히 소아 등에서는 갑상선 선량을 가능한 낮추어야 할 것이다.

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6MV 선형가속기에서 Al/Cu에 관한 여과판 사용시 전자오염 감소에 관한 연구 (Reduction of Electron Contamination in Photon Beam by electron Filter in 6MV Linear Accelerator)

  • 이철수
    • 대한방사선치료학회지
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    • 제8권1호
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    • pp.41-54
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    • 1996
  • The secondary electrons developed by interaction between primary beam and a tray mounted for blocks in Megavoltage irradiation result in excess soft radiation dose to the surface layer. To reduce this electron contamination, electron filters have been used to be attached under a tray. Various filters with Cu and Al plates in six different thickness and Cu/Al combined plates in 3 different thickness were tested to measure the reduction rate of secondary electron contamination to the surface layer. The measurement to find optimal filter was performed on 6MV linear accelerator in $10 cm{\times}10 cm$ field size and fixed 78.5cm source to measurement points distance from surface to maximum build up point in 2mm intervals. The result was analyzed as the ratio of measured doses with using filters, to standard doses of measured open beam. The result of this study was fellowing : 1. The contaminated low energy radiation were mainly produced by blocking tray. 2. The surface absorbed dose was slowly increased by increasing irradiation field size but rapidly increased at field size above $15cm{\times}15cm$. 3. Al plate upto 2.5mm thickness used as a filter was found to be inadequate due to the failure of reduction of the surface absorbed dose below doses of the under surface upto the maximal build up. Cu 0.5mm plate and Cu 0.28mm/A1 1.5mm compound plate were found to be optimal filters. 4. By using these 2 filters, the absorbed dose to the surface were effectively reduced $5.5\%$ in field size $4cm{\times}4cm,\;11.3\%$ in field size $10cm{\times}10cm,\;22.3\%$ in field size $25cm{\times}25cm$. 5. In field size $10cm{\times}10cm$, the absorbed dose to the surface of irradiation was reduced by setting TSD 20cm at least,. but effective and enough dose reduction could be achieved by setting TSD 30cm as 2 optimal filters used. 6. More surface dose absorbed at TSD less than 7.4cm with a tray and filters together indicated that soft radiation was also developed by filters. 7. The variation of PDD by the different size of irradiation field was minimal as 2 optimal filters used. There was also not different in variation of PDD according to using any of two different filters. 8. PDD was not effected either by various TSD or by using the different filter among two.

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RADIATION DOSE TO HUMAN AND NON-HUMAN BIOTA IN THE REPUBLIC OF KOREA RESULTING FROM THE FUKUSHIMA NUCLEAR ACCIDENT

  • Keum, Dong-Kwon;Jun, In;Lim, Kwang-Muk;Choi, Yong-Ho
    • Nuclear Engineering and Technology
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    • 제45권1호
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    • pp.1-12
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    • 2013
  • This paper describes the radiation doses to human and non-human biota in the Republic of Korea, as a result of the Fukushima nuclear accident. By using the measured airborne activity and ground deposition, the effective and thyroid doses of five human age groups (infant, 5 years, 10 years, 15 years and adult) were estimated by the ECOSYS code, and the whole body absorbed dose rate of the eight Korean reference animals and plants (RAPs) was estimated by the K-BIOTA (the Korean computer code to assess the risk of radioactivity to wildlife). The first-year effective and thyroid human doses ranged from 5.7E-5 mSv in the infant group to 2.0E-4 mSv in the 5 years group, and from 5.0E-4 mSv in the infant group to 3.4E-3 mSv in the 5 years group, respectively. The life-time (70 years) effective and thyroid human doses ranged from 1.5E-4 mSv in the infant group to 3.0E-4 mSv in the 5 years group, and from 6.0E-4 mSv in the infant group to 3.5E-3 mSv in the 5 years group, respectively. The estimated maximum whole body absorbed dose rate to the Korean RAPs was 6.7E-7 mGy/d for a snake living in soil (terrestrial biota), and 2.0E-5 mGy/d for freshwater fish (aquatic biota), both of which were far less than the generic dose criteria to protect biota from ionizing radiation. Also, the screening level assessment for ERICA's (Environmental Risks from Ionizing Contaminants: Assessments and management) limiting organisms showed that the risk quotient (RQ) for the estimated maximum soil and water activity was significantly less than unity for both the terrestrial and freshwater organisms. Conclusively, the radiological risk of the radioactivity released into the environment by the Fukushima nuclear accident to the public and the non-human biota in the republic of Korea is considered negligible.