• Title/Summary/Keyword: 치료용 방사성동위원소

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Analysis of Radiation Dose on Single Cells Using Therapeutic Radioisotopes Using the Monte Carlo Method (몬테카를로 방법을 이용한 치료용 방사성동위원소 사용 시 단일 세포에 대한 선량 분석)

  • Kim, Jung-Hoon;Kim, Yu-Soo
    • Journal of radiological science and technology
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    • v.45 no.5
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    • pp.433-438
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    • 2022
  • Targeted radionuclides treatment (TRT) requires the establishment of treatment plans that consider various factors, such as the type of radionuclides, target organs, and administration methods. For this reason, in this study, the absorption dose of a single cell was analyzed according to the type of radioisotope used to treat target radionuclides. In this study, a simulation was performed on beta rays used in the treatment of target radionuclides at the cell level using MCNPX (ver. 2.5.0). First, according to the calculation formula, the beam path according to the type of radioisotope for treatment was calculated. Second, the amount of self-radiation by beta rays emitted from cell diameters of 5 ㎛ and 10 ㎛ cell nuclei was evaluated. As a result, it showed a high range proportional to the maximum energy of the beta-ray, and the highest self-dose distribution from 177 Lu radiation sources among therapeutic radioisotopes. This was analyzed as a result that is inversely proportional to the maximum energy of the beta-ray, and it suggests that the selection of a nuclide considering the range of the beta-ray is necessary in the treatment of target radionuclides in the future.

Validation Study for Image Performance of I-131 Using GATE Simulation Program (GATE 시뮬레이션 프로그램을 이용한 I-131의 영상 특성의 타당성에 관한 연구)

  • Baek, Cheol-Ha;Kim, Dae Ho;Lee, Yong-Gu;Lee, Youngjin
    • Journal of the Institute of Electronics and Information Engineers
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    • v.54 no.5
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    • pp.133-137
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    • 2017
  • The purpose of this study was to validate for GATE (Geant4 Application for Tomographic Emission) simulation by comparing the results of GATE simulation and experiment in real SPECT system. Futhermore, we want to prove that it is possible that the quantitative research of gamma camera/SPECT imaging for therapeutic radio isotope by using GATE simulation. In this study, the SPECT system on simulation referred to the parameters of Stream-R Forte version 1.2 (Philips Medical System, Best and Heerlen, Netherlands). To understand the I-131 image of gamma camera/SPECT system, we acquired the energy spectrum and measured the full width at half maximum (FWHM) which comes from line spread function (LSF) with and without scatter material in real SPECT system. And to compare with experiment, we also measured the FWHM and acquired the energy spectrum without scatter material in GATE simulation. As a result, without scatter material, the energy peak was almost same location, which are located nearby 364 keV, and other spectrum factors are same tendency in both cases. The FWHM was increased by increasing the distance of source to detector, and the error rate was approximately 3.8%. When we used the line source with scatter material, energy spectrum also indicated similar tendency in both cases. As you confirmed earlier, GATE simulation included real instrument and radioisotope characters for therapeutic radioisotope. Therefore this result that it was possible that various quantitative study for therapeutic radioisotope imaging in gamma camera/SPECT using GATE simulation.

Quality Control Tests and Acceptance Criteria of Diagnostic Radiopharmaceuticals (진단용 방사성의약품의 품질관리시험 및 기준)

  • Park, Jun Young
    • Korean Journal of Clinical Laboratory Science
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    • v.53 no.1
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    • pp.1-10
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    • 2021
  • Radiopharmaceuticals are drugs that contain radioisotopes and are used in the diagnosis, treatment, or investigation of diseases. Radiopharmaceuticals must be manufactured in compliance with good manufacturing practice regulations and subjected to quality control before they are administered to patients to ensure the safety of the drug. Radiopharmaceuticals for administration to humans need to be sterile and pyrogen-free. Hence, sterility tests and membrane filter integrity tests are carried out to confirm the asepticity of the finished drug product, and a bacterial endotoxin test conducted to assess contamination, if any, by pyrogens. The physical appearance and the absence of foreign insoluble substances should be confirmed by a visual inspection. The chemical purity, residual solvents, and pH should be evaluated because residual by-products and impurities in the finished product can be harmful to patients. The half-life, radiochemical purity, radionuclidic purity, and strength need to be assessed by analyzing the radiation emitted from radiopharmaceuticals to verify that the radioisotope contents are properly labeled on pharmaceuticals. Radiopharmaceuticals always carry the risk of radiation exposure. Therefore, the time taken for quality control tests should be minimized and care should be taken to prevent radiation exposure during handling. This review discusses the quality control procedures and acceptance criteria for a diagnostic radiopharmaceutical.

Therapeutic radionuclides (치료용 방사성동위원소)

  • Choi, Sun-Ju;Hong, Young-Don;Lee, So-Young
    • Nuclear Medicine and Molecular Imaging
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    • v.40 no.2
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    • pp.58-65
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    • 2006
  • Since the development of sophisticated molecular carriers such as octereotides for peptide receptor targeting and monoclonal antibodies against various antigens associated with specific tumor types, radionuclide therapy (RNT) employing open sources of therapeutic agents is promising modality for treatment of tumors. furthermore, the emerging of new therapeutic regimes and new approaches for tumor treatment using radionuclide are anticipated in near future. In targeted radiotherapy using peptides and other receptor based tarrier molecules, the use of radionuclide with high specific activity in formulating the radiopharmaceutical is essential in order to deliver sufficient number of radionuclides to the target site without saturating the target. In order to develop effective radiopharmaceuticals for therapeutic applications, it is crucial to carefully consider the choice of appropriate radionuclides as well as the tarrier moiety with suitable pharmacokinetic properties that could result in good in vivo localization and desired excretion. Up to date, only a limited number of radionuclides have been applied in radiopharmaceutical development due to the constraints in compliance with their physical half-life, decay characteristics, cost and availability in therapeutic applications. In this review article, we intend to provide with the improved understanding of the factors of importance of appropriate radionuclide for therapy with respect to their physical properties and therapeutic applications.

고 선량율 근접 및 온열치료 병용 삽입관의 제작과 특성

  • 추성실;김성규
    • Proceedings of the Korean Society of Medical Physics Conference
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    • 2003.09a
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    • pp.52-52
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    • 2003
  • 악성종양을 치료하는 방법중 방사선과 온열요법은 가장 강력한 치료방법으로 연구되어왔으며 이를 병용함으로 서 상승효과를 얻을 수 있다. 인체조직에 41$^{\circ}C$ 이상의 열을 가하면 세포질의 단백질변성으로 세포에 손상을 주어 세포가 사멸하게 되며 세포의 생존율은 가열시간 즉 열량에 따라 지수적으로 감소한다. 온열은 세포주기중 방사선 저항성이 매우 큰 DNA 합성시기와 산도가 높을 때 감수성이 매우 크기 때문에 방사선과 병용요법은 상호 상승효과를 가져온다. 이와 같이 온열을 이용한 악성종양의 치료가능성은 생물학적 기초연구와 임상시험에서 경이적인 효과를 얻을 수 있었으나 아직 까지 가열방법과 온도분포측정이 큰 과제로 남아있으며 주위건강조직의 가열을 피하면서 인체 깊은 곳에 존재하는 종양에만 집중 가열하는 방법인 삽입형 온열치료방법에 대한 연구가 집중되었다. 한편 방사선 치료방법은 주위 건강조직의 피폭을 최소로 줄이고 종양에만 집중 조사가 요구되며 자궁암, 유방암, 뇌암등 부피가 작고 집중적 치료를 요하는 종양은 방사성동위원소를 이용한 근접 삽입치료 (Brachyradiotherapy)가 큰 효과를 나타내고 있다 방사선과 온열의 병행 치료를 위하여 방사선 삽입 치료에 사용한 선원 삽입관을 그대로 두고 삽입관 속에 방사성 동위원소 대신 온열 전극을 넣어 열을 가하는 방사선 온열 병용치료방법을 고안하였으며 방사선과 온열병용에 사용할 최적 삽입관의 제작과 이에 따른 온도분포의 측정과 최적삽입방법을 결정하였다. 방사선 삽입치료용 폴리에찌렌 삽입관의 외부에 금박을 입혀 라디오파 첨극을 삽입할 때 서로 연결되도록 고안 제작함으로서 방사선 삽입치료와 자입식 온열치료를 동시에 만족하게 수행할 수 있는 병용삽입관 (Flexible thermoradiotherapy probes)을 제작하였다. 전도율이 큰 금박부위가 직접 조직에 접촉됨으로 라디오파의 전달이 용이하며 금박의 길이를 2 cm 에서 5 cm 로 구분제작 함으로서 종양의 크기와 모양에 따라 선택할 수 있도록 하였다. 라디오파를 이용한 온열분포의 측정은 인체조직과 전기적 특성이 비슷한 물질인 한천 팬텀 제작하여 사용하였으며 온도분포 측정은 열전대와 서머그람으로 시행하였다. 생체조직 내에서의 온도분포와 온열효과를 관찰하기 위하여 직접 개의 뇌를 이용하여 시행하였으며 4 개의 전극을 이용하여 43$^{\circ}C$로 50분간 가열하고 일주일후 개를 회생시켜 개 뇌에 대한 조직학적 검사를 시행하였다. 한편 팬텀 표면에서 중앙부로 안테나 길이가 2 cm 인 4 개의 전극을 1 cm 간격으로 정사각형이 되도록 삽입하여 가열하였을 때 90% 등온곡선이 반경 1.25의 원형으로 균일하게 분포되었고 종단면상 삽입관의 길이에 따라 균일한 온도분포가 이루어졌다. 전극을 2 cm 간격으로 삽일 하였을 때 90% 등온곡선이 1.75 반경으로 거의 4 각형의 균일한 분포를 얻었으나 전극의 간격이 증가하면 전도율이 떨어져서 전극 중심부에 불균일한 온도분포를 형성하였다. 동물실험에서 정상 개의 뇌 실질에 자입하여 직접 정방형의 중심을 43$^{\circ}C$로 유지하며 50분간 온열 요법을 시행한 후 관찰한 조직병리학적 소견은 liquefactive necrosis, pyknosis of neuronal element 및 polymorphonuclear leukocytes들의 회백질에서 급성기에 관찰되었고 liquefactive necrosis 주위에 lipid-laden macrophage들이 관찰됨이 공통적인 특정이었으며 후기변화로 괴사조직 주위로 신경교세포의 증식이 관찰되었다.

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Analysis of Absorbed Dose on the Nucleus Size Change of Single Cells using Therapeutic Radioisotopes (치료용 방사성동위원소 사용 시 단일 세포의 핵 크기 변화에 따른 흡수선량 분석)

  • Uoo-Soo, Kim;Yong-In, Cho
    • Journal of the Korean Society of Radiology
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    • v.16 no.7
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    • pp.1007-1014
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    • 2022
  • Targeted radionuclide therapy (TRT) is a method of treating tumor cells using radiopharmaceuticals. Cells and nuclei constituting tissues of the human body are composed of spherical and oval shapes, but cancer cells are composed of various cell types. Therefore, this study analyzed the absorbed dose for each organelle according to the change in the size of the cell nucleus for beta-emitting nuclides during targeted radionuclide therapy through the Monte Carlo method. Cells were set in two sphere shapes, 5 ㎛ and 10 ㎛, and the internal structure was divided into cell nucleus, cytoplasm, and cell surface. Next, the absorbed dose according to the increase in the size of the cell nucleus was evaluated. As a result, 177Lu among the target radionuclides showed the highest dose in all cell compartments. As the ratio of the nucleus in the cell increased, the absorbed dose on the cell surface increased, but the absorbed dose in the cytoplasm and nucleus tended to decrease. Accordingly, it is judged that it is important to select a radionuclide considering the size of cancer cells and determine an appropriate amount of radioactivity during targeted radionuclide treatment.

Study of 188Re(V)-DMSA for Treatment of Cancer: Radiolabeling and Biodistribution (암 치료를 위한 188Re(V)-DMSA에 관한 연구: 방사성동위원소 표지와 생체내 분포)

  • Kim, Young Ju;Jeong, Jae Min;Chang, Young Soo;Lee, Dong Soo;Chung, June-Key;Lee, Myung Chul;Koh, Chang-Soon
    • The Korean Journal of Nuclear Medicine
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    • v.32 no.1
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    • pp.81-88
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    • 1998
  • The purpose of this study was to examine the radiolabeling and biodistribution of $^{188}Re(V)$-DMSA as a therapeutic cancer radiopharmaceutical. We made a DMSA kit($NaHCO_3$ 1.5 mg, meso-2,3-dimercaptosuccinic acid 1.0 mg, L(+)-ascorbic acid 0.7 mg, $SnCl_2{\cdot}2H_2O$ 0.34 mg, pH 2.9) for labeling with $^{188}Re$. In this kit, $^{188}ReO_4{^-}$ 5 mCi/2 ml added and boiled at $100^{\circ}C$ for 3 hr in water bath. The final pH adjusted to 7.5 with 7% $NaHCO_3$ solution. We checked the labelling efficacy with TLC-SG(n-butanol : acetic acid : $H_2O$ = 3 : 2 : 3) and examined the stability both in room temperature and in serum at $37^{\circ}C$. Biodistribution(1, 3, 13, 24, 48 hr) of $^{188}Re(V)$-DMSA compound was evaluated in Sarcoma 180 tumor-bearing mice. Each labeling efficiency and stability at room temperature for 48 hours was over 98% and 95%, respectively. The stability in serum were 82%(6 hr) and 85%(48 hr). Tumor uptake of $^{188}Re(V)$-DMSA in Sarcoma 180-bearing mice were $0.66{\pm}0.15%$(1 hr), $0.51{\pm}0.10%$(3 hr), $0.19{\pm}0.05%$(24 hr) and $0.13{\pm}0.02%$(48 hr). These result are consistent with those of $^{99m}Tc(V)$-DMSA which were reported previously. In conclusion, $^{188}Re(V)$-DMSA may be a useful therapeutic radiopharmaceutical for treating some cancers and metastatic bone lesion.

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