This study explores the effects of X-ray irradiation for biological control and high-temperature degradation on dye stability in dyed textiles with Gardenia. To evaluate this study, optimal extraction solvents for these textiles were identified by comparing them with a crocin standard solution. Extraction using pyridine closely matched crocin. The study then assessed the stability of X-ray irradiation and high-temperature degradation on these textiles. Transparent yellow dyes were observed in all samples. Color differences were found to increase at higher irradiation doses and longer degradation periods. While UV spectroscopy spectra showed broadening and lowering trends with higher irradiation doses and longer degradation periods, suggesting a reduction in colorant transition, mass spectrometry revealed minimal chemical changes. In conclusion, both X-ray irradiation and high-temperature degradation induced spectral changes without complete dye decomposition. Major colorants were consistently detected.
To establish a radioactive waste life cycle history management system, a series of processes including waste generation, classification, packaging, storage, transportation, and disposal were reflected in the information management system. A preliminary review process was introduced to reduce the amount of radioactive waste generated and manage it efficiently. Through this, the amount of radioactive waste generated must be checked from the beginning of the research, and the generated radioactive waste must be thoroughly managed from the stage of generation to final disposal. In particular, in the case of radioactive waste data generated during nuclear facility operation and each experiment, a radioactive waste information management system must be operated to receive information from the waste generator and integrate it with processing information at the management stage. The application process for small-package containers was reflected so that information such as the generation facility of radioactive waste, generation facility, project information, types of radioactive waste, major radionuclides, etc. In the radioactive waste management process, the preceding steps are to receive waste history from the waste generators. This includes an application for a specified container with a QR label, pre-inspection, and management request. Next, the succeeding steps consist of repackaging, treatment, characterization, and evaluating the suitability of disposal, for a process to transparently manage radioactive wastes.
Accidents at nuclear facilities and nuclear power plants led to leaks of large amounts of radioactive substances. Of the various radioactive nuclides released, 137Cs are radioactive substances generated during the fission of uranium. Therefore, due to the high fission yield (6.09%), strong gamma rays, and a relatively long half-life (30 years), a rapid and efficient removal method and a study of adsorbents are needed. Accordingly, an adsorbent was prepared using Prussian blue (PB), a material that selectively adsorbs radioactive cesium. As a result of evaluating the adsorption performance with the prepared adsorbent, it was confirmed that 82% of the removal efficiency was obtained, and most of the cesium was rapidly adsorbed within 10 to 15 minutes. The purpose of this study was to adsorb cesium using the Prussian blue alginate bead and to compare the change in detection efficiency according to the amount of adsorbent added for quantitative evaluation. However, in this case, it is difficult to determine the detection efficiency using a standard source with the same conditions as the measurement sample, so the efficiency change of the HPGe detector according to the different heights of Prussian blue was calculated through MCNP simulation using certified standard materials (1 L, Marinelli beaker) for radioactivity measurement. It is expected to derive a relational equation that can calculate detection efficiency through an efficiency curve according to the volume of Prussian blue, quantitatively evaluate the activity at the same time as the adsorption of radioactive nuclides in actual contaminated water and use it in the field of nuclear facility operation and dismantling in the future.
The Korean 2nd basic plan for management of high-level radioactive waste presented a plan to manage spent nuclear fuel through dry storage facilities in NPP on-site. For the construction and operation of the facility, it is necessary to develop the monitoring system of the integrity of spent nuclear fuel before operation. NUREG-1536 recommends that the theoretical cask array, typically in the 2×10 array, should account for shadowing effect among the dry storage casks. The objective of this study was to evaluate neutron flux accounting for shadowing effect among dry storage casks. The neutron release rate was evaluated using ORIGEN based on the design basis fuel condition. And the simulation of dry storage casks and evaluation of the shadowing effect were performed using MCNP. Shadowing effect of other dry storage casks was the highest at the center of the dry storage facility of the 2×10 array compared with the outside of the cask. The shadowing effect of neutron flux on the surface among the metal casks was approximately 18% at point 1, 23% at point 2, and 43% at point 3. For the concrete casks, the shadowing effect of neutron flux on the surface was approximately 46% at point 1, 51% at point 2, and 52% at point 3. This means that correction is necessary to monitor the integrity of spent nuclear fuel in each dry storage cask through evaluation of shadowing effect. The results of this study will be used for comparative analysis of neutron measurement data from spent nuclear fuels in dry storage cask. Additionally, the neutron flux evaluation procedure used in this study could be used as the basic data of safety assessment of dry storage cask and development of safety guide.
There are various factors that have a negative impact on safety over a long period of time after the closure of a radioactive waste disposal facility. In particular, it is important to limit substances that accelerate radionuclide migration while inhibiting adsorption between radionuclides and the subsurface medium. Through this study, a method for deriving a quantitative criteria evaluation method is proposed for cellulose among materials that accelerate the movement of these radionuclides after closure of the disposal facility. Since Sweden's SKB is representative worldwide for preparing criteria for cellulose in disposal facilities, it analyzed Sweden's acceptance criteria method and presented a method that can be applied domestically. The decomposition characteristics of cellulose and the adsorption and dissolution characteristics of ISA among degradation products were reviewed, and quantitative analysis of cement materials that create a high pH environment favorable for cellulose decomposition was also included. In addition, the total amount of the finally disposable cellulose material can be derived by using the volume information of the waste containing the cellulose material. Through this methodology for calculating the total amount of cellulose, it is expected that subsequent studies will be conducted to secure data reflecting the environmental conditions of radioactive waste disposal facilities in Korea. In addition, it is expected to be utilized as a good method to evaluate the impact of other complexing agents other than cellulose and to suggest the amount of disposal.
Thallium-201 (201Tl) is a medical radioisotope which emits gamma rays when it decays and used in myocardial perfusion scans in single-photon emission tomography due to its similar properties to potassium. Currently, the Korea Institute of Radiological & Medical Sciences is the only institution producing 201Tl in Korea, and optimization of 201Tl production research is necessary to meet supply compared to domestic demand. To this end, technical analysis of plating target production and chemical separation methods essential for 201Tl production research is conducted. It deals with the process of generating and separating 201Tl radioisotope and target production, It can be generated through a nuclear reaction such as natHg(p,xn)201Tl, 201Hg(p,n)201Tl, natPb(p,xn)201Bi → 201Pb → 201Tl, 205Tl(p,5n)201Pb → 201Tl, and considering impure nuclide generated simultaneously with the use of proton beam energy of 35 MeV or less, it is intended to be produced using the 203Tl(p,3n)201Pb→201Tl nuclear reaction. In particular, the chemical separation of Tl is a very important element, and the chemical separation methods that can separate it is broadly divided into four types, including solid phase extraction, liquid-liquid, electrochemical, and ion exchange membrane separation. Some chemical separations require additional separation steps, such as methods using selective adsorption. Therefore, this technical report describes four chemical separation methods and seeks to separate high-purity 201Tl using a method without additional separation steps
The uterus, one of women's reproductive organs, is also closely related to women's health. Among them, hemorrhagic luteal cysts, one of the causes of pelvic pain that women often experience, were observed through CT and ultrasound, and the quality of images was evaluated through quantitative and qualitative evaluations. This study sought to find out whether the test method is more helpful to patients during CT and ultrasound. This study was conducted on 15 adolescent women and 15 adult women(21.31±3.45 average age). The equipment used for filming used EC3-10X (3~10 MHZ) and Philips Mx8000 iCT 256 among Endocavity Probes among Ecube Platinum. After setting a constant ROI on the cyst and the interface as a quantitative analysis method, SNR and CNR values were measured on a 5-point scale based on image quality, lesion clarity, image distortion, clarity of the interface, and motion artifacts (p<0.05). Independent t-test and Mann Whiteny U were performed, and the statistical program used was noted when SPSS (Version 22.0 for windows software package, Chicago, IL, USA) was statistically less than 0.05. Comparing the SNR and CNR values for this experiment, it can be seen that the SNR value was higher in the case of CT images(p<0.05). As a result of the qualitative evaluation, the quality of the image, the clarity of the lesion, the distortion of the image, the clarity of the interface, and the clarity of the boundary were measured on a 5-point scale based on the movement artifact. Comparing each score, CT images scored higher with a finer difference than ultrasound images(p<0.05). In conclusion, both test methods showed excellent results in finding the patient's lesions. However, in quantitative and qualitative evaluations, CT produced higher results in detecting lesions than ultrasound. However, for cyst tests that require continuous observation, ultrasonography, a non-invasive method that is advantageous for patients, will be clinically useful. Therefore, observing the patient's lesions by appropriately distributing these two test methods will provide optimal diagnostic information. These results will be useful for providing clinical basic data and educational materials to CT and US users in the future.
From Cold War, Nuclear weapons have emerged military power into a very dangerous and important way of each national security. Throughout the era, the U.S. had stationed nuclear weapons in South Korea. But President George Bush initially started the withdrawal of nuclear tactical weapons deployed abroad in 1991. After that, under the protection of the nuclear umbrella, South Korea guarantees that the United States would operate its nuclear weapons to protect South Korea if it would be needed and the economy of South Korea has rapidly developed as more strong countries in the world. However, South Korea has seen and been realized the present state from the recent war between Russia and Ukraine. The protection of the U.S. nuclear umbrella from nuclear weapons and ballistic missiles of North Korea is unlikely to be permanently guaranteed. At the same time, South Korea should consider the security environment changes of surrounding nations such as China as military power acceleration and Russia as re-formation ambition. Because of these reasons, South Korea independently wants to protect itself and have the own nuclear weapons as a way to counter security threats. A majority of South Koreans also definitely believe that North Korea will not denuclearize or give up because North Korea has been having nuclear weapons as the final survival strategy of Kim Jong Un's regime. However, South Korea considers and makes new nuclear strategy through the role and effect of nuclear deterrence strategy in dispute between India and Pakistan and how to overcome the paradox of nuclear deterrence strategy. Therefore, this research is to suggest the effective nuclear deterrence strategy of South Korea from new security threats of surrounding nations through dispute between India and Pakistan. The focus of this research is that what is the role and paradox of nuclear deterrence strategy in dispute between India and Pakistan and how to find the effective nuclear deterrence strategy of South Korea.
Lutetium(177Lu), with its theranostic properties, is one of the most widely used radioisotopes and has a large share of the radiopharmaceutical market due to its many applications and targeted therapeutic research using lutetium-based radiopharmaceuticals. However, lutetium-based radiopharmaceuticals currently approved by the US Food and Drug Administration (FDA) are limited to the indications of gastrointestinal cancer, pancreatic neuroendocrine cancer and metastatic castration-resistant prostate cancer. To overcome these limitations, we aimed to demonstrate the feasibility of expanding the use of lutetium-based radiopharmaceuticals by verifying the availability and therapeutic efficacy of lutetium produced in a research reactor(HANARO). In this study, we confirmed the therapeutic efficacy of lutetium by using cancer cells from different types of cancer. In addition, we selected cancer biomarkers based on characteristics common to various cancer cells and compared and evaluated the therapeutic efficacy of lutetium by regulating the expression of target genes. The results showed that modulation of cancer biomarker gene expression resulted in higher therapeutic efficacy compared to lutetium alone. In conclusion, this study verified the potential use and therapeutic efficacy of lutetium based on the production of a research reactor (HANARO), providing fundamental evidence for the development of lutetium-based radiopharmaceuticals and the expansion of their indications.
The Non-Proliferation Treaty (NPT) is the basis of global efforts to prevent the spread of nuclear weapons. In Republic of Korea, safety measures are integrated with NPT approval through agreements with the International Atomic Energy Agency (IAEA) and the Safeguards Agreement. In contrast, Democratic People's Republic of Korea (DPRK), initially an NPT member, withdrew, refusing IAEA nuclear inspections. This inhibits the precise management of DPRK's nuclear facilities and limits access to related information. The Korean Peninsula, politically divided, sees DPRK in control of nuclear weapons. Although the IAEA periodically evaluates DPRK's nuclear facilities, there's a research gap in contamination and site management with nuclear activities. Recognizing the presence or absence of such activities is crucial for peaceful nuclear endeavors. This proposal suggests the number and locations for environmental sample collection using the Visual Sample Plan (VSP) software for nuclear activity analysis. VSP software is sample collection locations and quantities through statistical tests on collected data, ensuring reliability for decision-making. The proposal identifies sites and facilities for nuclear activity analysis based on IAEA safety reports, utilizing the software's embedded methods. Suggested sampling locations for undisclosed nuclear activities employ VSP's embedded techniques, including 'Show that at least some high % of the sampling area is acceptable' to confirm contamination and 'Estimate the Mean' to evaluate the average contamination level.
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