• 방사선산업학회지
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• 제18권2호
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• pp.127-132
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• 2024

Large amounts of liquid radioactive waste or radioactive contaminated water could be produced during the treatment of radiation accidents or during the dismantling and decontamination process of nuclear power plants. Since most of the decontamination agents to date are difficult to recover after adsorption of radioactive isotopes, their use in open environments such as rivers, reservoirs, or oceans is limited. In this study, as a radioactive decontamination agent that can overcome the current limitations when used in an open environment, a paramagnetic core inorganic composite (PMCIC) decomposite agent with high selectivity to cesium ions was developed. PMCore was prepared by synthesizing paramagnetic iron oxide nanoparticles, and inorganic crystals such as metal-ferrocyanide were conjugated to the surface so that PMCore could be selective to cesium ions. The developed PMCIC could be easily recovered from the water by magnetism and could adsorb up to 94 μM of Cs atoms per 1 g of PMCIC.

• Structural Engineering and Mechanics
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• 제65권2호
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• pp.203-211
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• 2018

This paper introduces the development process of NCC(New Concrete Cutting) system and analyzes first verification test. Based on the first verification test results, some problems of NCC system have been newly modified. We carry out the second verification test. We tried to verify cutting performance and dust control efficiency of NCC system through the cutting test of concrete bridge piers. In particular, this verification test strives to solve the problem of concrete dust, which is the biggest problem of dry cutting method. The remaining dust problems in cutting section tried to solve through this verification test. This verification test of the NCC system shows that the dust problem of dry cutting method is closely controlled and solved. In conclusion, the proposed NCC method is superior to the dry cutting method in all aspects, including cutting performance, dust vacuum efficiency and cooling effect. The proposed NCC system is believed to be able to provide eco-friendly cutting technology to various industries, such as the removal of the SOC structures and the dismantling of nuclear plants, which have recently become a hot issue in the field of concrete cutting.

• Nuclear Engineering and Technology
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• 제55권11호
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• pp.4181-4190
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• 2023

Nuclear power plants are subjected to various processes during decommissioning, including cutting, decontamination, disposal, and treatment. The cutting of massive bio-shields is a significant step in the decommissioning process. Cutting is performed near the target structure, and during this process, workers are exposed to potential radioactive elements. However, studies considering worker exposure management during such cutting operations are limited. Furthermore, dismantling a nuclear power plant under certain circumstances may result in the unnecessary radiation exposure of workers and an increase in secondary waste generation. In this study, a cutting scenario was formulated considering the bio-shield as a representative structure. The specifications of a standard South Korean radioactive waste disposal drum were used as the basic conditions. Additionally, we explored the hot-to-cold and cold-to-hot methods, with and without the application of polishing during decontamination. For evaluating various scenarios, different cutting time points up to 30 years after permanent shutdown were considered, and cutting speeds of 1-10nullm²/h were applied to account for the variability and uncertainty attributable to the design output and specifications. The obtained results provide fundamental guidelines for establishing cutting methods suitable for large structures.

• 한국환경보건학회지
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• 제17권1호
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• pp.95-103
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• 1991

For the purpose of estimating the working environment and the relationship between the airborne lead concentration and the ZPP level in the whole blood of the workers, the airborne lead concentrations and the ZPP level were measured at the 26 plants which deal with lead, from October 5 to November 5 in 1988. Analysis of the airborne lead concentration was performed by NIOSH Method 7082, and the ZPP level was measured by a hematofluorometer. The following results are concluded. 1. The average airborne lead concentration of the lead battery manufactures is 0.025mg/m$^{3}$ and that of the secondary lead smelters is 0.023mg/m$^{3}$. There were no significant differences between industry (p>0.1) 2. At the lead battery manufacture, the process of lead powder production showed the highest concentration of 0.034mg/m$^{3}$ but there were no significant differences among the processes (p>0.1). At the secondary lead smelter, the process of dismantling waste batteries showed the highest concentration 0.141mg/m$^{3}$, and there were very significant differences among the processes (p<0.005). 3. The ZPP level in the whole blood showed significant differences between industry (p<0.10). The average ZPP level of the lead battery manufactures is 133.0 + 106.3 $\mu$g/100ml and that of the secondary lead smelters is 149.6 + 110.9 $\mu$g/100ml. 4. The correlation coefficients between the airborne lead concantration and ZPP level were 0. 426 (p<0.001) for the lead battery manufactures and 0.484 (p<0.001) for the secondary lead smelters. The correlation coefficients between the work duration (in months) and the ZPP level were 0.238 (p<0.001) for the lead battery mannfactures and 0.075 (p>0.10) for the secondary lead smelters. 5. The linear regression equation, with the airborne lead concentration as an independent variable and the ZPP level as a dependent variable, is Y=96.84+1300.34X (r=0.448, p<0.001) for the 26 plants which deal with lead. The linear regression equation, with the work duration(in months) as an independent variable and the ZPP level as a dependent variable, is Y=127.28 +0.49X (r=0.162, p<0.05). 6. The correlation coefficients between the amount of inhaled lead and ZPP level were 0.349 (p < 0.001) for the lead battery manufactures and 0.318(p<0.001) for the secondary lead smeltes. The linear regression equation for the 26 plants surveyed, with the amount of inhaled lead as an independent variable and ZPP level as a dependent variable, is Y=123.63+18.82X (r=0. 335, p<0.001).

• 한국산업보건학회지
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• 제27권4호
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• pp.423-432
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• 2017

Objectives: This study was conducted to evaluate asbestos handling history of workers at automobile manufacturing plants in Korea. Methods: National regulations on asbestos and Korea Occupational Safety and Health Agency(KOSHA) database on the information of asbestos containing products were reviewed. We investigated asbestos related materials from one automobile manufacturing plant. Material safety data sheets(MSDS) collected in 2010, work environment monitoring results reported from 2000 to 2013, trade union reports and asbestos survey reports were reviewed. We also interviewed workers with long career and did walk-through survey. Results: The Ministry of Labor in Korea has permitted asbestos manufacturing since 1990. In 1997, the use of crocidolite and amosite asbestos were banned. In 2007, the Korean government announced a total ban on the manufacturing, importation and use of all kinds of asbestos, which took full effect in 2009. A total of 174 asbestos products information from KOSHA database was analyzed. Extruded cement panel for building, special brake for crane farm machinery, gasket, joint sheet and thermal insulator were produced until 2007. From automobile manufacturing plant survey, we confirmed that asbestos containing materials(ACM) such as gasket, heating induction materials have been used until 2011. Asbestos containing building materials(ACBM) such as bamlites, slate and ceiling tex were reported at 122 asbestos dismantling projects in 2014. Conclusion: Although the use of all kinds of asbestos were banned from 2009, ACMs and ACBMs installed before 2009 were still found at automobile manufacturing plant until 2011 and 2014 respectively. In particular, asbestos slates should be managed because most of slates had not been removed until 2014.

• 한국안전학회지
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• 제36권2호
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• pp.10-17
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• 2021

This paper presents the robust design of each component used in the development of an induction bolt heating system for dismantling the high-temperature high-pressure casing heating bolts of turbines in power plants. The induction bolt heating system comprises seven assemblies, namely AC breaker, AC filter, inverter, transformer, work coil, cable, and CT/PT. For each of these assemblies, the various failure modes are identified by the failure mode and effects analysis (FMEA) method, and the causes and effects of these failure modes are presented. In addition, the risk priority numbers are deduced for the individual parts. To ensure robust design, the insulated-gate bipolar transistor (IGBT), switched-mode power supply (SMPS), C/T (adjusting current), capacitor, and coupling are selected. The IGBT is changed to a field-effect transistor (FET) to enhance the voltage applied to the induction heating system, and a dual-safety device is added to the SMPS. For C/T (adjusting current), the turns ratio is adjusted to ensure an appropriate amount of induced current. The capacitor is replaced by a product with heat resistance and durability; further, coupling with a water-resistant structure is improved such that the connecting parts are not easily destroyed. The ground connection is chosen for management priority.

• 방사선산업학회지
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• 제18권1호
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• pp.89-93
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• 2024

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.

• 시스템엔지니어링학술지
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• 제17권1호
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• pp.65-75
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• 2021

When the decommissioning of South Korea nuclear power plants is promoted in earnest with the permanent shutdown of Kori Unit 1 in 2017, a large amount of various types of radioactive waste will be generated. For minimal generation and safe management of decommissioning waste, the waste should be made by appropriate classification of the dismantling waste characteristics in accordance with physical, chemical and radiological characteristics to meet the acceptance criteria of disposal facilities. Replacing the preliminary inspection at the site for the compliance of the waste acceptance criteria (WAC) of medium and low-level radioactive waste with the generator's own radioactive waste certification program (WCP), from the perspective of disposal, the optimization of waste management at the national level contributes to the efficient availability of disposal, such as the processing of non-conforming radioactive wastes at the site. To this end, it is important to evaluate radioactivity in each system and area such as nuclear reactors before decommissioning is carried out in earnest, and the prior removal of harmful wastes is important. From waste collection to waste disposal, decommissioning waste should be managed at each stage in consideration of the acceptance criteria of disposal facilities to minimize the generation of non-conforming waste.

• 자원리싸이클링
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• 제14권3호
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• pp.16-36
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• 2005

최근 들어 산업화된 국가에서 승용차의 대수는 비약적으로 증가하고 있으며 이러한 추세는 당분간 지속될 것으로 예상된다. 따라서 사용 후 폐기되는 자동차의 대수 또한 증가할 것이며 이를 재활용하는 문제가 심각히 제기되고 있다. 이러한 문제를 해결하기 위해 2000년 9월 유럽에서 제정된 폐기 자동차의 처리에 관한 규제 조항이 독일에서는 2002년 7월 1일부터 법률로서의 효력을 지니게 되었다. 이 법률 제정의 장기적 목표는 차후 10년 내에 폐자동차를 처리하는 과정에서 발생하는 잔류물을 현재의 30 Wt.%에서 5 t.% 미만으로 줄이는 데 있다. 따라서 차후 자동차를 구성하는 재료들에 대한 좀더 혁신적이고도 효율적인 재활용 기술에 대한 개발 필요성이 대두되고 있다. 자동차 생산 산업에서 디자인 공정은 계속하여 변화되고 있는 바, 이는 자동차 운행 시 연료를 절감하기 위한 선택적 장치와 새로운 기술적인 해결책에 대한 요구가 강하게 제기되고 있기 때문이다. 따라서 자동차 제조에 사용되는 재료로서 알루미늄과 플라스틱 등과 같은 가벼운 재료들의 사용량은 증가하고 있으며 철과 같은 무거운 재료들은 그 사용량이 점차 감소하고 있다. 그런데 자동차 구성 재료들 가운데 플라스틱류는 흔히 합성된 상태로 사용되고 있으므로 이를 기계적 방법에 의해 각각의 구성 플라스틱 성분으로 분리하기는 불가능하다. 이러한 이유로 인해 폐자동차를 구성하는 물질들의 효율적 재활용을 위해서는 재활용하기에 용이한 상태로 자동차를 디자인하여 제조하는 것이 필요하다고 할 수 있다. 이와 함께 폐자동차 재활용율을 향상시키는데 관한 규제를 만족시키기 위해서는 자동차 생산업체와 재황용 산업체의 통합적 협동체제가 요구된다.