• Title/Summary/Keyword: Lead-free Shielding

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A Study of Factors Affecting the Grid-test (X선격자 성능시험에 미치는 인자의 검토)

  • Lee, In-Ja;Shin, Wha-Soo;Kim, Chang-Kyun;Huh, Joon;Kang, Hong-Seok;Park, Jun-Chul;Yoon, Chul-Ho
    • Journal of radiological science and technology
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    • v.10 no.1
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    • pp.61-67
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    • 1987
  • Authors tested the grid functions with various thickness of acryl phantom, radiation field size and diameter of shielding lead. The results are as followed: 1. The characteristic values of grid are affected by phantom thickness, but free from radiation field size in the diagnostic useful range. 2. The quantity of scattered radiation was decreased according to the diameter of shielding lead under 20mm, and then the diameter the smaller the better, in accordance with proposed KS standard. 3. The quantity of primary radiation was increased a little at the 80mm diameter radiation field size, but did not have much differences. Therefore, it was thought that it is needed to limit beam size in case of absolute values in accordance with any standards, but it has no matter to use 100 mm diameter in case of relative values just to campare with.

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A Convenient Method on the Methyl-Ethyl-Ketone Extraction of $^{99m}TcO^-{_4}$ ($^{99m}TcO^-{_4}$의 메틸-에틸-케톤-간편 추출법)

  • Lee, Jong-Du;Lee, Byung-Hyn
    • Journal of Radiation Protection and Research
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    • v.9 no.2
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    • pp.103-111
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    • 1984
  • A convenient method of $^{99m}Tc$-methyl-ethyl-ketone (MEK) extraction technique was developed and a mobile $^{99m}Tc$-extraction generator was designed. The MEK extraction and the phase separation of $^{99m}TcO^-{_4}$ were carried out with a simple procedure in the same container. The shielding of $^{99}Mo$ radioactivity was made with one lead container. The system was simplified by shielding $^{99m}TcO_4{^-}({\gamma}_e=0.14\;MeV)$ separately. $^{99m}TcO^-{_4}\;in\;^{99m}Tc-MEK$ extract was recovered by adsorption and elution only, and therefore, the possibility of volatilization was reduced. The volume of $^{99m}TcO^{-}{_4}$-saline product was reduced to 1 ml by using a small alumina column and the column operation time was shortened. The separation time of $^{99m}Tc$ was reduced to 30 minutes, and the operation was carried out at the outside of the shielding. The system was designed to operate under the condition of bacteria-free.

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A Study on Reduction of Radiation Exposure by Nuclear Medicine Radiation Workers (핵의학 방사선 작업종사자 피폭 감소 방안에 대한 연구)

  • Lee, Wanghui;Ahn, Sungmin
    • Journal of the Korean Society of Radiology
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    • v.13 no.2
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    • pp.271-281
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    • 2019
  • This study investigated the shielding efficiency of various types of shielding materials and measured the dose by organ using the phantom. Results of Shielding Efficiency Measurement Using Personal Radiation Meter. Among the various shielding materials, 1.1 mm RNS-TX composed of nano tungsten showed the highest shielding efficiency and 0.2 mm lead shielding showed the lowest shielding efficiency. 99mTc 30 mCi was exposed to the phantom for 120 minutes and the result of the measurement of the organs. 20.53 mSv without radiation protective clothing, 8.75 mSv when wearing 0.25 mm Pb protective clothing, 6.03 mSv when wearing 0.5 mm Pb protective clothing. 131I 2 mCi mCi was exposed to the phantom for 120 minutes and the result of the measurement of the organs. 7.71 mSv without radiation protective clothing, 4.88 mSv when wearing 0.25 mm Pb protective clothing, 2.79 mSv when wearing 0.5 mm Pb protective clothing. 18F 5 mCi was exposed to the phantom for 120 minutes and the result of the measurement of the organs. 16.39 mSv without radiation protective clothing, 15.84 mSv when wearing 0.25 mm Pb protective clothing, 12.52 mSv when wearing 0.5 mm Pb protective clothing. None of the radiation workers working in the nuclear medicine department exceeded the dose limit. However, when compared with other workers in the hospital, they showed a relatively high dose. Therefore, it is necessary to prepare measures to reduce and manage the dose of radiation workers in the nuclear medicine department through the wearing of radiation protective clothing made of lightweight, shielding material with good shielding efficiency, circulation task, task sharing, and substitution equipment such as auto dispenser.

Development of a Flexible Eye Shield Phantom for Artifact-Free Computed Tomography Images

  • Seonghee Kang;Chang Heon Choi;Jung-in Kim;Geum Bong Yu;Jin Dong Cho
    • Progress in Medical Physics
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    • v.35 no.3
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    • pp.59-64
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    • 2024
  • Purpose: This study aimed to develop a flexible eye shield phantom to acquire artifact-free computed tomography (CT) images for electron beam radiotherapy. Methods: A flexible eye shield phantom for a newly designed eye shield was fabricated. Because of metal artifacts caused by an eye shield composed of high-density materials such as tungsten or lead, CT image acquisition is not appropriate for treatment planning because of inaccurate dose calculation and organ-at-risk delineation. To acquire artifact-free CT images, a mold of the same size as the outer dimension of the metallic eye shield was manufactured using 3D printing. The flexible eye shield phantom was imaged using a Philips Brilliance CT Big Bore under the same condition as the measurement. The phantom image with an average of 200 Hounsfield unit (HU) was imported into the treatment planning systems (TPS) and assigned a value of 26,750 HU to consider the material density of tungsten. The dosimetric comparison using a 6-MeV electron beam was performed. Measurement was performed using a metal oxide semiconductor field effect transistor detector for point doses at 3 and 10 mm. Results: The artifact-free CT images using a flexible eye shield phantom without air bubbles were transferred into the TPS. The dose at 10 mm calculated using the TPS agreed with the ion-chamber measurements within 2 cGy. Conversely, a larger dose discrepancy between the measured and calculated doses was found at 3 mm depth. Conclusions: The flexible eye shield phantom was successfully fabricated to apply electron treatment planning by acquiring artifact-free CT images. The dose calculated using the artifact-free image was comparable to the measured dose at lens depth when applying an eye shield.