• Proceedings of the Korean Society of Precision Engineering Conference
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• 2005.06a
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• pp.1699-1704
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• 2005

In this research the energy degrader, which is the most fragile part of the security of a target, has been newly designed to improve the performance of the gas target. Also, the numerical analysis of the heat movement and mechanical movement during the operation of the target has been accomplished. The heat analysis and structure analysis which are using the cooling water flow and pressure in the energy degrader and the Nastran mediocrity finite element analysis program, has been considered with the heat movement and mechanical movement according to the current capacity of proton beam which determines the production yield of the radioactive isotope. Also the possible use range has been determined, and at the same time the most suitable running condition according to the current capacity of proton beam has been suggested.

• Radiation Oncology Journal
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• v.6 no.2
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• pp.277-281
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• 1988

Although widely used in external beam treatment planning, computed tomography scans are infrequent in incranial tumors by implanting of Radioactive isotope. This incranial brachytherapy has only become possible by using CT scans and stereotaxic operation methods. The coincidence of single source and tumor axes in brachytherapy is very important to determine the therapeutic dosages. Eventhough using the CT scan, according to spatial location of tumor tying, the section of tumor will be seen enlargement, cause the tumor will be cut off with slight angle to its axes. Correct analysis of tumor size from source is required for rotated axes in analytical geometry.

• Journal of Radiopharmaceuticals and Molecular Probes
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• v.6 no.1
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• pp.46-52
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• 2020

Radiopharmaceuticals that can be consumed in specific disease site play a key role In order to diagnose and treat the diseases. In addition, radiopharmaceuticals can be used for diagnostic or therapeutic purposes depending on the type of the labeled radioactive isotope. Recently, theragnostic radiopharmaceuticals that can simultaneously diagnose and treat are developed. Therefore, the development of target-specific radiopharmaceuticals is a very important research topic in the field of molecular imaging and therapy. This review paper summarizes the basic considerations for the development of radiopharmaceuticals. For new researchers or students who are now beginning in the field of radiopharmaceuticals, we intend to assist in the development of radiopharmaceuticals by describing the definition of radiopharmaceuticals, the ideal radiopharmaceutical conditions, the considerations for developing new radiopharmaceuticals, the factors affecting the design of radiopharmaceuticals, the requirements of radioisotope labeling reactions, and finally the definition and importance of molar activity in radiopharmaceuticals.

• Nuclear Engineering and Technology
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• v.31 no.4
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• pp.365-374
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• 1999

A nuclear design of fission moly production targets for a research reactor, HANARO was peformed. It was found that the use of MCNP-4A, ORIGEN-2 code was reliable for the analysis of production characteristics of $^{99}$ Mo in a target fuel at an irradiation holes. A parametric study was done for the optimization of target location, target dimension, target shape and fuel materials. It was shown that a fuel thickness was the most sensitive parameters and electro-deposited target gave the highest 99Mo yield ratio. A pellet target with vibro-compaction powder, however, showed the largest production capacity and better engineering feasibility even with less yield ratio. Ten kinds of optimized target design for both LEU and HEU satisfied all the given design constraints. The most favorable design was the HEU ring-shaped electro-deposited target, considered the safety limit, production yield, chemical process easiness, yield ratio, and amount of radioactive waste.

• Journal of Veterinary Clinics
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• v.14 no.2
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• pp.230-234
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• 1997

In vitro effect of cortisol on the proliferation of canine peripheral blood mononuclear cells (MNC) was examined. The MNC was isolated from peripheral blood by a gradient centrifugation with Picoll-Hypaque. The cell proliferation assayed using a noneradioactive 5-Bromo-2'-deoxy-uridine (BrdU) kit. The MNC proliferated well in response to either phrtobeRagg$]$utinin-p (PHA-P) or culture supernatant from MNC stimulated with PHA-p. However, these proliferative responses of MNC were not affected by addition of coitisol of 1 to 1,OOfl ng/ml. The addition of cortisol in MNC culture with either PHA-P or corture supernatBnt from MNC stimulated with PHA-P far 4 days wag not also influenced on the viabilities of cultured MNC. In conclusions it was able to assay the cell proliferation with BrdU instead of radioactive isotope e.g. tritiated thymidine (3H-TdR). These results suggested that cortisol does not at least influence on MNC proliferation in vitro.

• Progress in Medical Physics
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• v.25 no.1
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• pp.8-14
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• 2014

The amounts of radioactive wastes to be disposed in the medical institute have been increased due to development of radiation diagnosis and therapy rapidly. They are produced mostly by the very short lived radioisotopes such as $^{18}F$ used in PET/CT, $^{99m}Tc$, $^{123}I$, $^{125}I$ and $^{201}Tl$, etc. IAEA proposed a criteria for the clearance level of waste which depends on the individual ($10{\mu}Sv/y$) and collective dose (1 man-Sv/y), and concentration of each nuclide (IAEA Safety Series No 111-P-1.1, 1992 and IAEA RS-G-1.7, 2004). Radioactive wastes of $^{18}F$, $^{99m}Tc$, $^{123}I$, $^{125}I$ and $^{201}TI$ in the several types of container like Marinelli beaker, vial and plastic, were collected to measure the concentration of the waste of each nuclide in accordance with IAEA criteria. The measurement method and procedure of determining specific activity of the wastes using gamma emitters like MCA, gamma counter and beta emitters were developed. For the efficiency calibration of the detectors, CRM (certified reference material) which has the same dimension and shape was provided by Korea Research Institute of Standards and Science (KRISS). Correction factor of the radioactivity decay was calculated based on the measurement results, and the consideration of mutual relation with theoretical equation. The result of this study will be proposed as ISO standard.

• Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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• 2002.07a
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• pp.62-66
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• 2002

The conventional floating zone(FZ) crystal and Czochralski(CZ) silicon crystal have resistivity variations longitudinally as well as radially The resistivity variations of the conventional FZ and CZ crystal are not conformed to requirement of dopant distribution for power devices and thyristors. These resistivity variations in conventional cystals limits the reverse breakdown voltage that could be achieved and forced designers of high power diodes and thyristors to compromise the desired current-voltage characteristics. So to produce high Power diodes and thyristors, Neutron Transmutation Doping(NTD) technique is the one method just because NTD silicon provides very homogeneous distribution of doping concentration. This procedure involves the nuclear transmutation of silicon to phosphorus by bombardment of neutron to the crystal according to the reaction $^{30}$ Si(n,${\gamma}$)longrightarrow$^{31}$ Silongrightarrow(2.6 hr)$^{31}$ P+$\beta$$^{[-10]}$ . The radioactive isotope $^{31}$ Si is formed by $^{31}$ Si capturing a neutron, which then decays into the stable $^{31}$ P isotope (i.e., the donor atom), whose distribution is not dependent on the crystal growth parameters. In this research, neutron was irradiated on FZ silicon wafers which had high resistivity(1000~2000 Ω cm), for 26 and 8.3hours for samples of HTS-1 and HTS-2, and 13, 3.2, 2.0 hours for samples of IP-1, IP-2 and IP-3, respectively, to compare resistivity changes due to time differences. The designed resistivities were approached, which were 2.l Ωcm for HTS-1, 7.21 Ω cm for HTS-2, 1.792cm for IP-1, 6.83 Ωcm for IP-2, 9.23 Ωcm for IP-3, respectively. Point defects were investigated with Deep Level Transient Spectroscopy(DLTS). Four different defects were observed at 80K, 125K, 230K, and above 300K.

• Korean Journal of Fisheries and Aquatic Sciences
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• v.41 no.2
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• pp.89-93
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• 2008

Goldfish were exposed to radioactive isotope $^{18}F$, which is used for positron emission tomography (PET). $^{18}F$ is created when the oxygen in water combines with hydrogen on exposure to positrons accelerated by a cyclotron. The temporal change in intestine contractility was measured by physiograph after the exposure to $^{18}F$. The distance between the goldfish and 580 mCi of $^{18}F$ was approximately 4 cm and the exposure was for 4 hrs. The absorption level calculated from the distance, exposure time, and half-life of $^{18}F$ was approximately 2 Gy. The contractile activity of goldfish intestine was lowest on the first day and increased gradually to 100% of the control level by a period of between 5 and 36 days.

• Nuclear Engineering and Technology
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• v.55 no.4
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• pp.1476-1484
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• 2023

Laboratory experiments and point monitoring of reservoir sediments have proven that stable sulfate reduction (SSR) can lower the concentrations of toxic metals and sulfate in acidic groundwater for a long time. Here, we hypothesize that SSR occurred during in situ leaching after uranium mining, which can impact the fate of acid groundwater in an entire region. To test this, we applied a sulfur isotope fractionation method to analyze the mechanism for natural attenuation of contaminated groundwater produced by acid in situ leaching of uranium (Xinjiang, China). The results showed that δ³⁴S increased over time after the cessation of uranium mining, and natural attenuation caused considerable, area-scale immobilization of sulfur corresponding to retention levels of 5.3%-48.3% while simultaneously decreasing the concentration of uranium. Isotopic evidence for SSR in the area, together with evidence for changes of pollutant concentrations, suggest that area-scale SSR is most likely also important at other acid mining sites for uranium, where retention of acid groundwater may be strengthened through natural attenuation. To recapitulate, the sulfur isotope fractionation method constitutes a relatively accurate tool for quantification of spatiotemporal trends for groundwater during migration and transformation resulting from acid in situ leaching of uranium in northern China.

• Journal of radiological science and technology
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• v.39 no.4
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• pp.557-564
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• 2016

Effects of Gamma camera imaging on gamma ray counting rates as a function of use and density of the iodine contrast medium currently in primary use for clinics, and changes in gamma ray counting rates as a function of the contrast medium status upon attenuation correction using a CT absorption coefficient in an SPECT/CT attenuation correction will be considered herein. For experimental materials used $^{99m}TcO_4$ 370 MBq and Pamiray 370 mg, Iomeron 350 mg, Visipaque 320 mg, Bonorex 300 mg of iodine contrast medium. For image acquisition, planar imaging was consecutively filmed for 1, 2, 3, 4, 5 min, respectively, 30 min after administration of $^{99m}TcO_4$. while 60 views were filmed per frame for 20 min at 55 min for the SPECT/CT imaging. In planar imaging, the gamma ray counting rates as a function of filming time were reduced showing a statistically significant difference when mixed according to the type of contrast medium density rather than when the radioactive isotope $^{99m}TcO_4$ and the saline solution were mixed. In the tomography for mixing of the radioactive isotope $^{99m}TcO_4$ and saline solution, the mean counting rate without correction by the CT absorption coefficient is $182{\pm}26counts$, while the counting rate with correction by the CT absorption coefficient is $531.3{\pm}34counts$. In the tomography for mixing of the radioactive isotope $^{99m}TcO_4$ and the saline solution with the contrast medium, the mean values before attenuation correction by CT absorption coefficient were $166{\pm}29$, $158.3{\pm}17$, $154{\pm}36$, and $150{\pm}33counts$ depending on the densities of the contrast medium, while the mean values after attenuation correction were $515{\pm}03$, $503{\pm}10$, $496{\pm}31$, and $488.7{\pm}33counts$, showing significant differences in both cases when comparatively evaluated with the imaging for no mixing of the contrast medium. Iodine contrast medium affects the rate of gamma ray. Therefore, You should always be preceded before another test on the day of dignosis.