• Journal of Radiopharmaceuticals and Molecular Probes
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• v.3 no.1
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• pp.18-24
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• 2017

Patient-specific image-based internal dosimetry involves using the patient's individual anatomy and spatial distribution of radioactivity over time to obtain an absorbed dose calculation. Individual absorbed dose was calculated by accumulated activity multiply S-value of each organs. The aim of this study was to calculate the S-values using Monte Carlo simulation in monkey and mouse and evaluation of absorbed dose in each organ. Self-irradiation S-value of monkey heart self-irradiation was 3.15E-03 mGy-g/MBq-s, lung self-irradiation was 8.94E-04 mGy-g/MBq-s and liver self-irradiation S-value was 2.23E-03 mGy-g/MBq-s. Mouse heart self-irradiation S-value was 1.95E-01 mGy-g/MBq-s, lung was 9.59E-02 mGy-g/MBq-s, and liver was 1.40E-03 mGy-g/MBq-s. The results of this study show that the calculation protocol of image based individual absorbed dose of each organ using Monte Carlo simulation. Therefore, this study may be applied to calculate human specific absorbed dose.

• Progress in Medical Physics
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• v.18 no.4
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• pp.187-193
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• 2007

In an effort to assess the internal absorbed dose of radionuclides that is suitable to Koreans' physiological characteristics, we asked 28 male Koreans to take $^{131}|$ orally, determined the thyroidal uptake and daily urination ratio, and assessed the absorbed dose by organ. As a result, first, 24 hours after administering, the average thyroidal uptake and the daily urination ratio registered 19.70% and 71.12%, respectively. Second, the whole body effective dose according to the thyroidal uptake calculated herein and the existing ICRP-suggested thyroidal uptake of 30% offered 1.464E-08 Sv and 2.189E-08 Sv, respectively, showing a 1.5 times difference. To evaluate the quantity of the absorbed dose of radioactive iodine, we can better reduce the error in assessing the body exposure dose by conducting measurement according to human races rather than depending on the existing ICRP data.

• Journal of the Korean Society of Radiology
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• v.10 no.4
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• pp.271-278
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• 2016

This study was fulfilled to evaluate the absorbed dose of breast and adjacent organs using MIRD type phantom in brachytherapy of breast cancer. The absorbed dose was analyzed assuming left or right breast is source organ which is $^{103}Pd$ or $^{192}Ir$. As a result, $^{192}Ir$ dose is higher than $^{103}Pd$ in source organ and also in contralateral breast. Particularly, significant adjacent organs are lung, liver, heart and contralateral breast in brachytherapy of breast cancer.

• Journal of radiological science and technology
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• v.43 no.6
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• pp.443-451
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• 2020

This study is to evaluate absorbed dose from right lung for brachytherapy and to estimate the effects of tissue heterogeneities on dose distribution for Iridium-192 source using Monte Carlo simulation. The study employed Geant4 code as Monte Carlo simulation to calculate the dosimetry parameters. The dose distribution of Iridium-192 source in solid water equivalent phantom including aluminium plate or steel plate inserted was calculated and compared with the measured dose by the ion chamber at various distances. And the simulation was used to evaluate the dose of gamma radiation absorbed in the lung organ and other organs around it. The dose distribution embedded in right lung was calculated due to the presence of heart, thymus, spine, stomach as well as left lung. The geometry of the human body was made up of adult male MIRD type of the computational human phantom. The dosimetric characteristics obtained for aluminium plate inserted were in good agreement with experimental results within 4%. The simulation results of steel plate inserted agreed well with a maximum difference 2.75%. Target organ considered to receive a dose of 100%, the surrounding organs were left the left lung of 3.93%, heart of 10.04%, thymus of 11.19%, spine of 12.64% and stomach of 0.95%. When the statistical error is performed for the computational human phantom, the statistical error of value is under 1%.

• Journal of radiological science and technology
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• v.35 no.4
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• pp.327-333
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• 2012

Purpose: To analyze the correlation between dose volume histograms(DVH) based on organ outer wall contour and organ wall delineation for bladder and rectum, and to compare the doses to these organs with the absorbed doses at the bladder and rectum. Material and methods: Individual CT based brachytherapy treatment planning was performed in 13 patients with cervical cancer as part of a prospective comparative trial. The external contours and the organ walls were delineated for the bladder and rectum in order to compute the corresponding dose volume histograms. The minimum dose in 0.1 $cm^3$, 1 $cm^3$, 2 $cm^3$, 5 $cm^3$, 10 $cm^3$ volumes receiving the highest dose were compared with the absorbed dose at the rectum and bladder reference point. Results: The bladder and rectal doses derived from organ outer wall contour and computed for volumes of 2 $cm^3$, provided a good estimate for the doses computed for the organ wall contour only. This correspondence was no longer true when large volumes were considered. Conclusion: For clinical applications, when volumes smaller than 5 $cm^2$ are considered, the dose-volume histograms computed from external organ contours for the bladder and rectum can be used instead of dose -volume histograms computed for the organ walls only. External organ contours are indeed easier to obtain. The dose at the ICRU rectum reference point provides a good estimate of the rectal dose computed for volumes smaller than 2 $cm^2$ only for a midline position of the rectum. The ICRU bladder reference point provides a good estimate of the dose computed for the bladder wall only in cases of appropriate balloon position.

• Journal of radiological science and technology
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• v.45 no.4
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• pp.331-339
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• 2022

The purpose of this study was to evaluate maternal organ and fetal doses by week of pregnancy for pregnant women nuclear medicine practitioners in the nuclear medicine field. In addition, we intend to present basic data for the management of exposure doses of female nuclear medicine practitioners. In this study, phantoms of childbearing women, 3, 6, 9 months pregnant women were simulated using MCNPX(Monte Carlo N-Particle Extended) among the Monte Carlo methods. First, volume source was constructed based on 10 cm of the anterior part of the lower abdomen of the phantom, and the organ and fetal doses were evaluated for each week of the pregnant woman according to the type of radioactive isotope. Second, the organ and fetal dose of pregnant women were evaluated by increasing the distance between the source and the abdominal surface by 50 and 100 cm. As a result, ¹⁸F sources showed high organ and fetal doses in pregnant women 0 to 3 months, and the dose distribution gradually decreased in 6 to 9 months pregnant women. The distribution of organ and fetal doses for ⁹⁹mTc and ¹²³I sources showed the same tendency as that of ¹⁸F, and the overall absorbed dose distribution was relatively lower than that of ¹⁸F. Through this study, it is considered that workers in the early stages of pregnancy within 3 months will need appropriate management to minimize occupational exposure dose.

• Journal of the Korean Society of Radiology
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• v.13 no.2
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• pp.247-252
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• 2019

This study was evaluated absorbed dose according to the gold nanoparticle density in prostate brachytherapy which was constantly occurred in Korean men. Absorbed dose evaluation was using MCNPX program which was applied Monte Carlo simulation. Source were applied $^{192}Ir$ which was temporary insertion source and $^{103}Pd$ which was permanently insertion source. And gold nanoparticle density was applied 0 mg, 7 mg, 18 mg and 30 mg. The prostate absorbed dose was increased in proportion to the density 2.95E-14 Gy/e to 4.42E-14 Gy/e in $^{192}Ir$ and showed the same tendency in $^{103}Pd$. And surrounding organ absorbed dose was inversely proportional to the density. Therefore using nanoparticle in brachytherapy was increased therapeutic ratio.

• Journal of the Korean Society of Radiology
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• v.8 no.4
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• pp.155-161
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• 2014

Mammography is mostly performed by series projection on both breasts. While taking mammography, it is less than average glandular dose of 3 mGy which regulated. But mammography is exposed much more doses actually, due to additional or series projection. Also, it is difficult to recognize around organ dose except exposed breast. Using mathematical simulation of radiation exposure body in mammography, we studied around organ dose distribution by changing thickness(25, 30, $50{\mu}m$) of filter and relative absorption dose rate which set on basis of exposed breast. as a result, when setting of basis of exposed breast, dose of opposite breast is more affected approximately from 79.26 to 86.31%. when using $25{\mu}m$ of filter thickness than $30{\mu}m$, $50{\mu}m$ of filter thickness in Mo/Mo, W/Rh combination which used actually, absorbed dose rates for opposite breast and around organ were low.

• Radiation Oncology Journal
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• v.16 no.4
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• pp.517-529
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• 1998

Purpose : Although many studies have investigated the dosimetric aspects of stereotactic radiosurgery in terms of target volume, the absorbed doses at extracranial sites: especially the lens or thyroid - which are sensitive to radiation for deterministic or stochastic effect -have infrequently been reported. The aim of this study is to evaluate what effects the parameters of radiosurgery have on the absorbed doses of the lens and thyroid in patients treated by stereotactic radiosurgery, using a systematic plan in a humanoid phantom. Materials and Methods : Six isocenters were selected and radiosurgery was planned using the stereotactic radiosurgery system which the Department of Therapeutic Radiology at Seoul National University College of Medicine developed. The experimental radiosurgery plan consisted of 6 arc planes per one isocenter, 100 degrees for each arc range and an accessory collimator diameter size of 2 cm. After 250 cGy of irradiation from each arc, the doses absorbed at the lens and thyroid were measured by thermoluminescence dosimetry. Results : The lens dose was 0.23$\pm$0.08$\%$ of the maximum dose for each isocenter when the exit beam did not pass through the lens and was 0.76$\pm$0.12$\%$ of the maximum dose for each isocenter when the exit beam passed through the lens. The thyroid dose was 0.18$\pm$0.05$\%$ of the maximum dose for each isocenter when the exit beam did not pass through the thyroid and was 0.41$\pm$0.04$\%$ of the maximum dose for each isocenter when the exit beam Passed through the thyroid. The passing of the exit beam is the most significant factor of organ dose and the absorbed dose by an arc crossing organ decides 80$\%$ of the total dose. The absorbed doses of the lens and thyroid were larger as the isocenter sites and arc planes were closer to each organ. There were no differences in the doses at the surface and 5 mm depth from the surface in the eyelid and thyroid areas. Conclusion : As the isocenter and arc plane were placed closer to the lens and thyroid, the doses increased. Whether the exit beams passed through the lens or thyroid greatly influenced the lens and thyroid dose. The surface dose of the lens and thyroid consistently represent the tissue dose. Even when the exit beam passes through the lens and thyroid, the doses are less than 1$\%$ of the maximum dose and therefore, are too low to evoke late complications, but nevertheless, we should try to minimize the thyroid dose in children, whenever possible.

• Progress in Medical Physics
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• v.19 no.3
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• pp.172-177
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• 2008

As a part of estimating quantitative radiation treatment doses, we produced a mathematical phantom based on the standard Korean male. Then, with the prostate as the source organ, we calculated the absorbed dose in the prostate and surrounding organs forecasted to occur during brachytherapy for prostate cancer. To simulate the procedure, we selected $^{25}I$ and $^{103}Pd$ useful in brachytherapy of the prostate as the radionucleids and made an assumption that 1 Ci of initial radioactivity is administered. As a result, we found that the prostate, as the source organ, indicated 101 Gy/Ci and 7.24 Gy/Ci, respectively, in case of $^{125}I$ and $^{103}Pd$. With the exception of the prostate, organs with high absorbed doses were found to be in the order of the penis and scrotum, sigmoid colon, testicles and the urinary bladder, which are relatively close to the prostate.