• Journal of the Korea Organic Resources Recycling Association
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• v.11 no.1
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• pp.84-89
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• 2003

The purpose of this study was to evaluate and improve the pre-treatment facility for foodwaste and sewage sludge mixture treatment. The process of foodwaste pre-treatment consists of storage, classification with crushing, and thickening. The effluent of sewage treatment facility was used as the diluting and washing water. The panicle size of foodwaste after pre-treatment was almost under 2mm, the mixture of foodwastes and sewage sludge showed an advantage to the anaerobic digestion. The amount of gas production increased from 0.8ton/day ($CH_4$ : 0.5ton/day) to 3.5ton/day ($CH_4$ : 2.3ton/day) after the anaerobic digestion of the foodwastes and sewage sludge mixture. The amount of sludge cake increased from 11.2ton/day to 21.2ton/day. Therefore, the proper operation of the foodwaste pre-treatment facility was contributed to the efficient anaerobic digestion of foodwaste and sewage sludge mixture treatment.

• Journal of Radiation Industry
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• v.18 no.1
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• pp.95-100
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• 2024

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.

• The Korean Journal of Nuclear Medicine Technology
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• v.17 no.1
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• pp.3-6
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• 2013

Purpose: The treatment of thyroid cancer patients was continuously increased. According to the increment of thyroid cancer patients, the establishment of iodine therapy site was also increased in each hospital. This treatment involves the administration of radioactive iodine, which will be given in the form of a capsule. Therefore, protections and managements for radioactive source pollution and radiation exposure should be necessary for radiation safety. Among the many problems, the problem of disposing the radioactive wastes was occurred. In this study, The date for self-disposal for radioactive wastes, which were contaminated in clothes, bedclothes and trash, were calculated. Materials and Methods: The number of iodine therapy ward was 15 in Korea Institute of Radiological Medical and Sciences. Recently, 8 therapy wards were operated for iodine therapy patients and others were on standby for emergency treatment ward of any radiation accidents. Radioactive wastes, which were occurred in therapy ward, were clothes, bedclothes, bath cover for patients washing water and food and drink which was leftover by patients. Each sample was hold into the marinelli beaker (clothes, bedclothes, bath covers) and 90 ml beaker (food, drink, and washing water). The activities of collected samples were measured by HpGe MCA device (Multi Channel Analysis, CANBERRA, USA) Results: The storage period for the each kind of radioactive wastes was calculated by equation of storage periods based on the measurement outcomes. The average storage period was 60 days for the case of clothes, and the maximum storage period was 93 days for patient bottoms. The average storage period and the maximum storage period for the trash were 69 days and 97 days, respectively. The leftover foods and drinks had short storage period (the average storage period was 25 days and maximum storage period was 39 days), compared with other wastes. Conclusion: The proper storage period for disposing the radioactive waste (clothes, bedclothes and bath cover) was 100 days by the regulation on self-disposal of radioactive waste. In addition, the storage period for disposing the liquid radioactive waste was 120 days. The current regulation for radioactive waste self-disposing was not suitable for the circumstances of each radioactive therapy facility. Therefore, it was necessary to reduce the leftover food and drinks by adequate table setting for patients, and improve the process and regulation for disposing the short-half life radioactive wastes.

• Korean Institute of Interior Design Journal
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• v.20 no.5
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• pp.197-207
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• 2011

In general, collections in museum are kept in storage according to a preservation and administration program in long or short term, after conservators' conservation treatment. Museum activities related to conservation science are common to do before and after exhibitions. That is, the museum collections include a flow mechanism, which circulate a space in where conservation science related activity is carried on centering around its storage. The purpose of this study is to suggest the design guidelines of a conservation area in a museum. The results of this study as follows. First, to program space planning, conservation area of museum is divided into 4 kinds of zone. Second, space for relics unloading in basically includes 'unloading room', 'control room', 'worker room', 'unpacking room', and 'unloading tools storage' and considers to install 'outdoor arrangement space', etc. In case of space for making relics collections, 'arrangement room' and 'temporary storage' are separately planned in order to arrange and temporarily store relics taken in. Conservation analysis space should be divided into 2 kinds of zone, 'conservation analysis lab' for analysis of collection characters and 'restoration lab' for conservation treatment in the bigger museum. In case of large-scale museum, conservation treatment space is basically classified with characters of museum collections. And it considers installing 'waterlogged wood lab', 'painting clothes treatment lab', 'storage of treated relics' etc. Third, for 'the spaces for analysis treatment', must consider activity contents and sizes of the department for scientific conservation every museum, can classify in detail required space, and must review the space for relics settlement in construction.

• Journal of the Korean Institute of Gas
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• v.21 no.3
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• pp.39-45
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• 2017

The LNG storage tank as core facility of LNG industry is mainly composed of the inner tank of nikel 9% steel and the outer tank of prestressed concrete. To respond proactively increased risk of structure performance deterioration due to fatigue of the inner tank and durability reduction of the outer tank, life evaluation program for LNG storage tank is needed. In this study, life evaluation program for LNG storage tank was developed to assess fatigue of the inner tank and durability(carbonation and chloride attack) of the outer tank. By defining the main three scenarios in the inner tank, the fatigue life analysis is conducted from structural analysis and Miner's damage rule. Carbonation progress of the outer tank is predicted according to thickness of cover concrete by using carbon dioxide contents and data of penetration depth. To consider a variety of input conditions and a reliability in results of chloride attack, the evaluation of choride attack for the outer tank is constructed through Life-365 program of open source.

• Fire Science and Engineering
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• v.20 no.4 s.64
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• pp.125-130
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• 2006

Pumped storage power plant is a system of generating electricity with hydroelectric power, in which at times of low electrical demand such as during nights, excess generation capacity of many power plants is used to pump water into the higher reservoir, and when there is higher demand, water is released back into the lower reservoir through a turbine, generating electricity. As pumped storage power plants across the nation are not on building registry under "the Article 6 of the Special Act by the Development of Power Resources", they are classified as a structure, not as a building. As a result, permit of fire protection facility is unnecessary, and fire protection administration is excluded from approval to completion of construction. Therefore, this study is to improve problems in accordance with the application of "he Article 6 of the Special Act by the Development of Power Resources", repair of facilities and problems with safety control to effectively prevent similar damages from repeatedly happening to pumped storage power plants in operation or under construction nationwide during a fire.

• Fire Science and Engineering
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• v.32 no.3
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• pp.60-66
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• 2018

Museum storage has been a unique area for experts, such as curators and managers etc., is a part that requires attention among the recent changes in museums because of changes to a type that is being opened gradually to visitors. On the other hand, there is an increased the risk of a fire according to negligence etc. of visitors. Hence, appropriate measures for a fire protection system to respond to varying museum storage are required. This study examined the status of fire protection systems applied to museum storage visiting 40 domestic public museums with the support of the Ministry of Culture, Sports and Tourism, and a direction to install a fire protection system was presented by drawing cases of fire protection systems with less adaptability or poor management or excellent fire protection systems, and a direction for improvement was presented.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.18 no.2_spc
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• pp.317-325
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• 2020

The Korea Radioactive Waste Agency plans to expand the storage capacity of radioactive waste by constructing a radioactive waste inspecting building to solve the problem of the lack of inspection space and drum-handling space in the radioactive waste receipt and storage building for the first-stage disposal facility. In this study, the exposure doses of radiation workers that handle new disposal containers for decommissioning waste in the storage areas of the radioactive waste inspecting building were calculated using the Monte Carlo N-particle transport code. The annual collective dose was calculated as a total of 84.8 man-mSv for 304 new disposal containers and an estimated annual 306 working hours for the radiation work. When the 304 new disposal containers (small/medium type) were stored in the storage areas, it was found that 25 radiation workers should be involved in acceptance/disposal inspection, and the estimated exposure dose per worker was calculated as an average annual value of 3.39 mSv. When the radiation workers handle the small containers in high-radiation dose areas, the small containers should be shielded further by increasing the concrete liner thickness to improve the work efficiency and radiation safety of the radiation workers. The results of this study will be useful in establishing the optimal radiation working conditions for radiation workers using the source term and characteristics of decommissioning waste based on actual measurements.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.2
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• pp.105-115
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• 2012

Necessity of demonstration test to evaluate the structural integrity of a basket for accident conditions arose during license approval procedure for the WSPP's dry storage facility named MACSTOR/KN-400. A drop test facility for demonstration was constructed in KAERI site and demonstration tests for basket drop were conducted. As the upper welding region of a loaded basket was collided with a dropped basket during the drop test, the welding in this region was fractured and leakage happened after the drop test. The enhancement of basket design was needed since the existing basket design was not able to satisfy the performance requirement. The directions for design modification were determined and six enhanced designs were derived based on these directions. Structural analyses and specimen tests for each enhanced design were conducted. By evaluating structural analysis results and test results, one among six enhanced designs was decided as a final design for revision. The final design was the one to reduce the height of central post of a basket and to decrease the impact velocity with a dropped basket. Test basket models were fabricated with accordance with the final enhanced design. Additional demonstration test was performed for this test model and all the performance requirements were satisfied.

• Journal of Korean Society of Disaster and Security
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• v.16 no.1
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• pp.61-70
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• 2023

This study presents an analytical study of investigating the effect of shock waves generated by the hydrogen detonation and damage to structures for the safety evaluation of hydrogen storage facilities against detonation. Blast scenarios were established considering the volume of the hydrogen storage facility of 10 L to 50,000 L, states of charge (SOC) of 50% and 100%, and initial pressures of 50 MPa and 100 MPa. The equivalent TNT weight for hydrgen detonation was determined considering the mechanical and chemical energies of hydrogen. A hydrogen detonation model for the converted equivalent TNT weight was made using design equations that improved the Kingery-Bulmash design chart of UFC 3-340-02. The hydrogen detonation model was validated for overpressure and impulse in comparison to the past experimental results associated with the detonation of hydrogen tank. A parametric study based on the blast scenarios was performed using the validated hydrogen detonation model, and design charts for overpressure and impulse according to the standoff distance from the center of charge was provided. Further, design charts of the three-stage structural damage and standoff distance of adjacent structures according to the level of overpressure and impact were proposed using the overpressure and impulse charts and pressure-impulse diagrams.