• Journal of Radiopharmaceuticals and Molecular Probes
• /
• v.3 no.2
• /
• pp.80-84
• /
• 2017

Re-188 is an excellent and practical radioisotope produced by W-188/Re-188-generator for therapy. We prepared Re-188-tin colloid for therapy of various diseases and tried to treat peritoneal effusion in animal model. Sarcoma-180 cells were injected into ICR mice to induce peritoneal effusion and the mice were grown for 3 d. Re-188-tin colloids (0.25, 0.5, and 1 mCi/mL per 30 g body weight) were injected into the mice and the mice were grown for 90 d. Planar gamma scintigraphy showed even distribution of Re-188-tin colloid radioactivity. Bax expression was found to be dose dependent to Re-188-tin colloid. Normal saline treated group showed the shortest survival time. Among the treated groups, 0.5 mCi dose group showed the longest survival time. In conclusion, Re-188-tin colloid was prepared successfully and showed the feasibility to use as a peritoneal effusion treatment in mice.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.11a
• /
• pp.47-55
• /
• 2005

A design of a dismantling mock-up system have been established based on the result that analyzed a characteristic of modules which need to design a virtual dismantling facility. A unit program composed of a various module such as a decommissioning database system. 3D dosimetric mapping that represents a distribution of a radionuclide contamination, a evaluation module for a dismantling schedule and cost A research of software architecture was carried out in order to Integrate these components that have been independently operated. The result was established an architecture that consis of a visualization module which could be visualized D&D activities and a simulation module which tan he evaluated a dismantling schedule and decommissioning cost.

• The Korean Journal of Nuclear Medicine
• /
• v.24 no.2
• /
• pp.293-298
• /
• 1990

We performed 17 intraarterial scintigraphies in six patients with recurrent cervix cancer. With Seldinger method, the agent (four different radiopharmaceuticals) was perfused at the same speed of infusion of anticancer drugs (25 cc/hour) through internal iliac artery. There were four different radiopharmaceuticals; I-131-Lipiodol, Tc (Technetium)-99m-HSa (Human Serum Albumin), $^{99m}Tc-Sucralfate$ and $^{99m}Tc-MAA$ (Macroaggraegated Albumin). We evaluate the distribution pattern of radioactivity by the use of ratio of Tumor/Extratumor uptake (T/ET ratio). Our results reveals that $^{99m}Tc-MAA$ scan showed the highest T/ET ratio and the other were not ideal agents for intraarterial therapy of recurrent cervix cancer. In conclusion, an ideal radioisotope and tracer which can block capillary, for example MAA, should be re-evaluated or produced in order to treat the patient with recurrent cervix cancer.

• Nuclear Engineering and Technology
• /
• v.27 no.1
• /
• pp.1-7
• /
• 1995

The mechanism of radionuclide colloid transport in porous media was studied through modeling and experiment. A nondestructive column scanning system was developed to improve the traditional destructive core slicing method. With an aid of this system we could get much more results from one experiment. Neutron activated clay soaked with soluble isotopes was used as colloid suspension. Filtration coefficients obtained through the experiments show two families of colloids despite their size distribution. New modeling of polydispersed colloid transport was made with two lumped parameters. This new model simulates well. Among the soluble isotopes $^{l37}$Cs mowed mainly as a form of colloid, but $^{85}$ Sr did not.t.

• Nuclear Engineering and Technology
• /
• v.51 no.4
• /
• pp.1041-1046
• /
• 2019

In terms of long-term safety for radioactive waste disposal, the anionic iodide (I-129) with a long half-life ($1.6{\times}10^6yr$) is of a critical importance because this radionuclide migrates in geological media with limited interactions. Various studies have been performed to retard the iodide migration. Recently, some minerals that are likely generated from waste container corrosion, have been suggested to have a considerable chemical interaction with iodide. In this study, chalcocite and mackinawite were selected as candidate minerals for underground corrosion materials, and an iodide sorption experiment were carried out. The experiment was performed under anoxic and alkaline conditions and the pH effects on the iodide sorption were investigated in the range of pH 8 to 12. The results showed that both minerals demonstrated a noticeable sorption capacity on iodide, and the distribution coefficient ($K_d$) decreased as the pH increased in the experimental condition. In addition, when the alkalinity increased higher than a pH of 12, the sorption capacity of both minerals decreased dramatically, likely due to the competition of hydroxy ions with the iodide. This result confirmed that chalcocite was an especially good sorbing media for iodide under alkaline conditions with a pH value of less than 12.

• Nuclear Engineering and Technology
• /
• v.54 no.7
• /
• pp.2736-2747
• /
• 2022

The operations in the design lifecycle of a nuclear power plant targeted to be decommissioned lead to neutron activation. Operations in the decommissioning process include cutting, decontamination, disposal, and processing. Among these, cutting is done close to the target material, and thus workers are exposed to radiation. As there are only a few studies on pressurizers, there arises the need for further research to assess the radiation exposure dose. This study obtained the specifications of the AP1000 pressurizer of Westinghouse and the distribution of radionuclide inventory of a pressurizer in a pressurised water reactor for evaluation based on literature studies. A cutting scenario was created to develop an optimal method so that the cut pieces fill a radioactive solid waste drum with dimensions 0.571 m × 0.834 m. The estimated exposure dose, estimated using the tool VISIPLAN SW, in terms of the decontamination factor (DF) ranged from DF-0 to DF-100, indicating that DF-90 and DF-100 meet the ICRP recommendation on exposure dose 0.0057 mSv/h. At the end of the study, although flame cutting was considered the most efficient method in terms of cutting speed, laser cutting was the most reasonable one in terms of the financial aspects and secondary waste.

• Journal of radiological science and technology
• /
• v.45 no.5
• /
• pp.433-438
• /
• 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.

• Nuclear Engineering and Technology
• /
• v.54 no.12
• /
• pp.4715-4721
• /
• 2022

A comprehensive approach for modeling the pulse height spectra of gamma-ray detectors from passing radioactive cloud in a case of accident at NPP has been developed. It involves modeling the transport of radionuclides in the atmosphere using Lagrangian stochastic model, WRF meteorological processor with an ARW core and GFS data to obtain spatial distribution of radionuclides in the air at a given moment of time. Applying representation of the cloud as superposition of elementary sources of gamma radiation the pulse height spectra are calculated based on data on flux density from point isotropic sources and detector response function. The proposed approach allows us to obtain time-dependent spectra for any complex radionuclide composition of the release. The results of modeling the pulse height spectra of the scintillator detector NaI(Tl) Ø63×63 mm for a hypothetical severe accident at a NPP are presented.

• Journal of Radiation Protection and Research
• /
• v.10 no.2
• /
• pp.109-112
• /
• 1985

Radioisotope tracer experiments on the distribution and the binding of radionuclides to proteins in bivalve were carried out in order to gain further information on biochemical behavior of radionuclides in marine bivalve, Gomphina melanaegis. The radioactivities (cpm/g) of $^{65}Zn\;and\;^{54}Mn$ after 7 days exposure were highly concentrated in liver and kidney in comparison to soft parts. The gel filtration profile of $^{65}Zn$ in liver and kidney showed three elution peaks, while $^{54}Mn$ showed two peaks in liver and three peaks in kidney. On the gel filtration of $^{137}Cs$ in liver and kidney, most of $^{137}Cs$ were eluted on one peak. Thus, it was considered that each radionuclide was bound to different proteins in liver and kidney of bivalve.

• The Journal of Engineering Geology
• /
• v.26 no.1
• /
• pp.71-78
• /
• 2016

This study aimed to evaluate the occurrence of natural radionuclides in Korean groundwater. Groundwater radionuclide data for the period 2000-2011 were obtained from the National Institute of Environmental Research and published literature, classified into five groups according to host rock type, and used to construct detailed concentration maps. Radon, uranium, gross-α, and radium concentrations ranged from 0.4 to 64,688.0 pCi/L (mean: 4,907 pCi/L), 0 to 2,297 μg/L (mean: 27.5 μg/L), 0 to 312 pCi/L (mean: 3.9 pCi/L), and 0 to 17.4 pCi/L (mean: 0.2 pCi/L), respectively. Radon concentrations in 562 of a total 1,501 wells (i.e., 53.5%) exceeded 4,000 pCi/L, which is the acceptable contamination threshold established by the United States Environmental Protection Agency. Uranium, gross-α, and radium concentrations exceeded the respective thresholds of 30 μg/L, 15 pCi/L, and 5 pCi/L in 121 of 1,031 wells (11.9%), 34 of 978 wells (3.5%), and 4 of 89 wells (4.5%), respectively. The mean radionuclide concentration in groundwaters hosted by igneous and metamorphic rocks was higher than that in groundwaters hosted by other rock types, such as volcanics, carbonates, and other sedimentary rocks. The correlations between individual radionuclides were weak or insignificant.