• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.24-31
• /
• 2004

In order to decommission safely nuclear power plant, it is necessary for the procedure of residual radioactivity investigation in site to provide detailed guidance for planning, implementing, and evaluating environmental and facility radiological surveys conducted to demonstrate compliance with a dose or risk-based regulation. This study presents the procedure of residual radioactivity investigation in decommissioning site - Historical Site Assessment, Scoping Survey, characterization Survey, Remedial Action Support Survey, Final Status Survey - on the basis of MARSSIM(Multi-Agency Radiation Survey and Site Investigation Manual) and investigation cases of decommissioned or decommissioning nuclear power plant.

• Journal of Radiation Protection and Research
• /
• v.24 no.2
• /
• pp.109-120
• /
• 1999

Residual radiation and radioactivity level in TRIGA Mark-II, III research reactors and facilities at the KAERI Seoul site, which are to be decommissioned, have been measured, analyzed and evaluated to know the current status of radiation and radioactivity level and to establish and to provide the technical requirements for the safe decommissioning of the facilities which shall be applied in minimizing the radiation exposure for workers and in preventing the release of the radioactive materials to the environment. Radiation dose rate and surface radioactivity contamination level on the experimental equipments, floors, walls of the facilities, and the surface of the activated materials within the reactor pool structure were measured and evaluated. Radioactivity and radionuclides in the pool and cooling water were also analyzed. In case of the activated reactor pool structures which are very difficult to measure the radiation and radioactivity level, a computer code Fispin was additionally used for estimation of the residual radioactivity and radionuclides. The radiation and radioactivity data obtained in this study were effectively used as basic data for decontamination and dismantling plan for safe decommissioning of TRIGA Mark-II, III facilities.

• Archives of Pharmacal Research
• /
• v.9 no.3
• /
• pp.157-161
• /
• 1986

Isolated calf thymus nuclei were in vitro methylated with S- adenosy-L-methyl-$^{14}C$ methionine, and the proteins were fractionated according to their solubilities. Histone fraction ($H_{2}SO_{4}$-soluble fraction) contained approximately 60% total radioactivity incorporated, while "residual protein" which was ($H_{2}SO_{4}$-insoluble contained the remaining radio-activity. The "residual protein" was further fractionated into various acidic proteins, which contained very littel of the radioactivity. However, the protein fraction eluted from DEAE-cellulose with 0.5 N NaOH contained the largest amount of radioactivity. This protein was found to be basic in nature by amino analysis.

• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.05a
• /
• pp.265.1-265.1
• /
• 2004

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2018.05a
• /
• pp.377-378
• /
• 2018

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.21 no.4
• /
• pp.481-487
• /
• 2023

Concerning the apprehensions about naturally occurring radioactive materials (NORM) residues, the International Atomic Energy Agency (IAEA) and its member nations have acknowledged the imperative to ensure the radiation safety of NORM industries. Residues with elevated radioactivity concentrations are predominantly produced during NORM processing, in the form of scale and sludge, referred to as technically enhanced NORM (TENORM). Substantial quantities of TENORM residues have been released externally due to the dismantling of NORM processing factories. These residues become concentrated and fixed in scale inside scrap pipes. To assess the radioactivity of scales in pipes of various shapes, a Monte Carlo simulation was employed to determine dose rates corresponding to the action level in TENORM regulations for different pipe diameters and thicknesses. Onsite gamma spectrometry was conducted on a scrap iron pipe from the titanium dioxide manufacturing factory. The measured dose rate on the pipe enabled the estimation of NORM concentration in the pipe scale onsite. The derived action level in dose rate can be applied in the NORM regulation procedure for on-site judgments.

• Journal of the Korean Society of Radiology
• /
• v.16 no.2
• /
• pp.95-102
• /
• 2022

This study compares the difference between the remaining amount in syringes according to injection method and the dose of physiological saline when the radiopharmaceutical ¹⁸F-FDG isotope is injected into patients who visited the hospital for PET examination. After performing a CT or MRI using a contrast medium when ¹⁸F-FDG was injected into 40 patients who came to the hospital for PET examination without removing the 3-way, the radioactivity remaining in the syringe and the 3-way was measured and the dose of radioactivity confirmed. At this time, 20 patients were divided into different dose groups of physiological saline. Another injection method was used to compare the remaining amount of the syringe and the difference in the remaining amount according to the amount of physiological saline when the injection was performed with an extension. After an injection of ¹⁸F-FDG, the actual administered dose was confirmed by measuring the radioactivity remaining in the syringe and the 3-way or extension with a calibrator. As a result of measuring the radioactivity of the syringe before administering the radiopharmaceutical and the radioactivity of the syringe and the 3-way or extension after administration, the 3-way injection method in 10 cc's of physiological saline had the lowest residual amount. The remaining amount increased in the order of the extension to 10 cc's of saline and the 3-way to 5 cc's of saline. Likewise, the 5 cc's saline solution and the extension injection method demonstrated the highest residual amounts. The residual difference with the lowest level of remaining injection method was found to be 0.053 mCi. It was found that in a PET examination, by considering the radioactivity remaining in the 3-way and extension and by adjusting the dose of physiological saline, if the intended dose to be administered to the actual patient is determined, it is possible to administer the radiopharmaceutical to the patient more accurately.

• Journal of Mushroom
• /
• v.18 no.4
• /
• pp.387-392
• /
• 2020

Eight dried ear mushroom products (three domestic and five Chinese products) distributed in Korea were analyzed for 321 residual pesticides, 7 heavy metals, and 3 types of radioactivity. Residual pesticides in the domestic products were not detected. However, chlorpyrifos, isoprocarb, mepiquat chloride, and carbendazim were detected in four Chinese products, all of which were below the allowable residual limit. Among the detected pesticide ingredients, only the residue for mepiquat chloride has been established to be present in ear mushrooms. In the heavy metal test, trace amounts of heavy metals were detected in all samples. However, none of the samples exceeded the allowable residual limits, except for one domestic sample that exceeded the standard value of 0.3 mg/kg for lead. Radioactivity tests confirmed that levels were below the minimal detectable activity value in all samples.

• Journal of the Korean Society of Radiology
• /
• v.17 no.5
• /
• pp.701-707
• /
• 2023

In PET/CT, the injection volume of ¹⁸F-FDG directly affects the SUV(standard uptake value), which can affect the reading results. Therefore, it is important to inject the correct dose value of ¹⁸F-FDG. In this study, we performed the correlation between the residual radioactivity remaining in the syringe and catheter insertion device according to the number of flushing during ¹⁸F-FDG injection. CRC-25R dose calibrator, catheter insertion devices, 3 cc syringes and 50 cc physiological saline were used in this study, and the results were statistically analyzed. As a result, the total residual radioactivity of the syringe and catheter insertion device remained the highest at 5.84% after two flushing, and the least remained at 1.49% after five flushing. The correlation analysis results showed that the number of flushing had a negative correlation with the residual radioactivity of the syringe at -0.436 and the catheter insertion device at -0.300. As a result of one-way distributed analysis of the average according to the number of flushing, the syringe showed a significant decrease at 4 times, and the catheter insertion device showed a significant decrease at 5 times. However, considering that an average of 0.8% remains in the case of catheter insertion devices, four time flushing seems to be the most appropriate.

• Journal of Radiation Protection and Research
• /
• v.38 no.4
• /
• pp.228-233
• /
• 2013

It has been continuously generated the requirement for the replacement of the main components such as a steam generator due to the deterioration of the nuclear power plant all around the world. Also, a large amount of radioactive metal was generated during the decommissioning in a short period. It is required to make an accurate measurement of the residual radioactivity for recycling the metal waste for releasing from regulatory control. In planning the measurement procedures, the influence of geometry, self-absorption, density and other relevant factors on the representativeness of the measurements should be considered for the decommissioning metal waste. In this study, the method for measurement procedures, the source term evaluation, the ways to secure representative samples, the measurement device for wide area and the self-absorption correction factors for different density were evaluated. The metal samples for measurement were prepared for securing the simple geometry and representative by melting process. The developed correction method for measuring the radioactivity a variety density of metal waste could improve the reliability of the evaluation results for clearance.