• 제목/요약/키워드: Spent filter

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Current Status of the Spent Filter Waste and Consideration of Its Treatment Method in KAERI (KAERI 저장 폐필터의 현황과 처리방법에 관한 고찰)

  • Ji, Young-Yong;Hong, Dae-Seok;Kang, Il-Sik;Shon, Jong-Sik
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.3
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    • pp.257-265
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    • 2007
  • Spent filter wastes of about 1,000 units (200 L) have been stored in the waste storage facility of the Korea Atomic Energy Research Institute since its operation. At the moment, to secure space in a waste storage facility as well as to efficiently manage spent filter wastes, it is necessary to conduct a compaction treatment of these spent filters, and finally, to repack the compacted spent filters into a 200 liter drum. To do that, the spent filter wastes were first classified according to their generation facilities, their generation date and their surface dose rate by investigating the inventory of the spent filters. In order to repack a compacted spent filter in a 200 liter drum, it is first necessary to conduct a radionuclide assessment of a spent filter before compacting it. Therefore, after taking a representative sample from a spent filter without a dismantlement, the nuclide analysis for it will be conducted. And then, after putting a spent filter into a regular drum by conducting the columnar shaping of the hexahedral form of a spent filter, the compaction treatment of the shaped spent filter will be conducted by vertically compacting it.

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Design of a HEAP Filter Assembly for Air-Filter in Nuclear Power Plant (원자력 발전소 공기 조화용 HEPA 필터 설계)

  • Park, Jong-Beom;Kwon, Tae-Jong;Moon, Ki-Won;Lee, Se-Yup
    • Proceedings of the KIEE Conference
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    • 2000.07b
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    • pp.781-783
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    • 2000
  • In developing the assemble HEPA(High Efficiency Particulate Air) Filter, the main frame and sub frame can be easily assembled and disassembled and tightly sealed. The sub frame(included Media) will be made of the manageable material. so it will be easily compacted with the spent filter compactor. It does not take a lot of time for disassembling the spent filter. The main frame can be recycled and the volume of the spent filter is reduced, so the cost for treating the radioactive waste is reduce. And the changing costs can be reduced, because the cost of the media is lower than the filter.

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A Study on the Pretreatment of the Spent Coffee Grounds using Electrocoagulation and Its Filter Characteristics (전기 응고법을 이용한 커피박의 전처리 및 기능성 필터 특성 연구)

  • Park, Soobin;Han, Haneul;Park, Haneul;Lim, Seunghyun;Yoo, Bongyoung;Yoon, Sanghwa
    • Journal of the Korean institute of surface engineering
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    • v.54 no.4
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    • pp.209-214
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    • 2021
  • As coffee consumption per person increases annually to 323 cups in 2018, treating the spent coffee ground has arisen because spent coffee ground results in soil and air pollution. The demands of air purification filters are increasing more and more because the air pollution due to the fine dust has become worse. The spent coffee grounds had a porous structure, however, the pore was blocked by organic oil compounds. Electrocoagulation, which is one of the electrochemical methods, has the potential to remove the organic compounds. The surface area of spent coffee grounds increased effectively after the electrocoagulation treatment, and surface morphology and surface area were confirmed using SEM and BET, respectively. Using the FT-IR, both the spent coffee grounds and the electrocoagulated spent coffee grounds were characterized. The filter characteristics were examined by the adsorption test using formaldehyde, one of the air pollutants.

Suggestion of Efficient High Dose Spent Filter Handling and Compaction Equipment

  • Lee, Kyungho;Chung, Sewon;Park, Seonghee;Kim, HuiGyeong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.2
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    • pp.243-253
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    • 2022
  • Spent filters with a high radiation dose rate of 2 mSv·hr-1 or more are not easily managed. So far, the Korean policy for spent filter disposal is to store them temporarily at nuclear power plants until the waste filters can be easily managed. Nuclear power plant decommissioning in Korea is starting with Kori unit 1. Volume reduction of waste generated during decommissioning can reduce the cost and optimize the space usage at disposal site. Therefore, efficient volume reduction is a very important factor during the decommissioning process. A conceptual method, based on the experiences of developing 200 and 800 ton compactors at Orion EnC, has been developed considering worker exposure with the followings a crusher (upgrade of compaction efficiency), an automatic dose measuring system with a NaI(Tl) detector, a shield box, an inner drum to prepare for easy handling of drums and packaging, a 30 ton compactor, and an automatic robot system. This system achieves a volume reduction ratio of up to 85.7%; hence, the system can reduce the disposal cost and waste volume. It can be applied to other types of wastes that are not easily managed due to high dose rates and remote control operation necessity.

Study on the Institutional Control Period Through the Post-drilling Scenario Of Near Surface Disposal Facility for Low and Intermediate-Level Radioactive Waste (중·저준위 방사성폐기물 천층처분시설에서 시추 후 거주시나리오 평가를 통한 폐쇄 후 제도적 관리기간 연구)

  • Hong, Sung-Wook;Park, Jin-Baek;Yoon, Jung-Hyun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.1
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    • pp.59-68
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    • 2014
  • The public's access to the disposal facilities should be restricted during the institutional control period. Even after the institutional control period, disposal facilities should be designed to protect radiologically against inadvertent human intruders. This study is to assess the effective dose equivalent to the inadvertent intruder after the institutional control period thorough the GENII. The disposal unit was allocated with different kind of radioactive waste and the effects of the radiation dose to inadvertent intruder were evaluated in accordance with the institutional control period. As a result, even though there is no institutional control period, all were satisfied with the regulatory guide, except for the disposal unit with only spent filter. However, the disposal unit with only spent filter was satisfied with the regulatory guide after the institutional control period of 300 years. But the disposal unit with spent filter mixed with dry active waste could shorten the institutional control period. So the institutional control period can be reduced through the mixing the other waste with spent filter in disposal unit. Therefore, establishing an appropriate plan for the disposal unit with spent filter and other radioactive waste will be effective for radiological safety and reduction of the institutional control period, rather than increasing the institutional control period and spending costs for the maintenance and conservation for the disposal unit with only spent filter.

Thermal Stress Analysis of Spent Fuel Vol-oxidizer Furnace on the Internal Pressure (내부 압력변화에 대한 사용후핵연료 분말화장치 가열로의 열 응력 해석)

  • Kim, Y.H.;Jung, J.H.;Hong, D.H.;Park, B.S.;Lee, J.K.;Yoon, J.S.
    • Proceedings of the Korean Society for Technology of Plasticity Conference
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    • 2006.05a
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    • pp.136-140
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    • 2006
  • We are developing a vol-oxidizer which transforms the spent $UO_2$ pellets into the $U_3O_8$ power through oxidizing process. The vol-oxidizer consists of furnace, filter, heater and valve etc. When the filter is blocked by the powder, the internal pressure of the furnace is increased owing to the air flow restriction. Then, the furnace vessel is swelled and deformed by it. In this paper, we proposed a procedure of the thermal analysis for furnace vessel design of spent fuel vol-oxidizer. In this work, we determined the thickness of the furnace through analyzing the internal pressure and the thermal stress of the furnace with respect to various pressure and temperature. To analyze the thermal stress, we used ANSYS 8.0 for constructing a FEM model of the furnace, and then analyzed it based on the ASME code. We also surveyed the material property and yield stress of SUS304 with various temperature. Analysis results are compared with the yield stress of the material. We manufactured the furnace and conduct the verification experiments.

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Analysis on the heat-resisting method of the electrolytic metal reduction reactor in the test facility for the spent fuel waste (사용후핵연료 시험시설에서 전기 금속 전환반응기의 내열 방안 분석)

  • 김영환;윤지섭;정재후;홍동희;박기용;진재현
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2003.06a
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    • pp.776-779
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    • 2003
  • To reduce the storage space of spent fuel used at the atomic power plants in the over the world, the uranium elements contained in the spent fuel is being extracted and effectively stored. For this, the spent fuel are oxidized and deoxidized. In this study, it is produced the heat-resisting methods about the spent fuel management technology research and test facility for the spent fuel waste for spent fuel minimized. The first considered processes in the facility are the electrolytic metal reduction reactor process. Since the electrolytic metal reduction reactor is operated at the high temperature range, we have to consider the heat-resisting methods for the devices. For the heat-resisting methods, we have searched and analyzed technical reference for the heat-resisting methods. We have calculated thermal stress and strain of each devices by the commercial analysis software, ANSYS. D.S. It is experimented for inspecting confidence rate of analysis results. By using the results, we have analyzed the problems of parts and determined the heat-resisting material, commercial parts, and the size of parts and O-ring. Based on these results, it is produced the heat-resisting methods of magnesia filter, cathode, and reactor for the electrolytic metal reduction reactor.

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A Shared Compliant Control Scheme based on Internal Model Control

  • Ahn, Sung-Ho;Jin, Jae-Hyun;Park, Byung-Suk;Yoon, Ji-Sup
    • 제어로봇시스템학회:학술대회논문집
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    • 2003.10a
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    • pp.1571-1574
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    • 2003
  • A shared compliant control scheme based on IMC is proposed for the position-force force reflecting control system. The controller of the slave manipulator is designed by IMC method for the open loop unstable plant. The compliant control is implemented by first order low pass filter. In the proposed scheme, the slave manipulator well tracks the position of the master manipulator in free space and the compliance of the slave manipulator is autonomously controlled in contact condition. The simulation results show that the excellence of the proposed controller.

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Efficient Recovery of Lignocellulolytic Enzymes of Spent Mushroom Compost from Oyster Mushrooms, Pleurotus spp., and Potential Use in Dye Decolorization

  • Lim, Seon-Hwa;Lee, Yun-Hae;Kang, Hee-Wan
    • Mycobiology
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    • v.41 no.4
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    • pp.214-220
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    • 2013
  • This study was conducted in order to perform efficient extraction of lignocellulolytic enzymes amylase (EC 3.2.1.1), cellulase (EC 3.2.1.4), laccase (EC 1.10.3.2), and xylanase (EC 3.2.1.8) from spent mushroom compost (SMC) of Pleurotus ostreatus, P. eryngii, and P. cornucopiae. Optimal enzyme recovery was achieved when SMCs were extracted with 50 mM sodium citrate (pH 4.5) buffer at $4^{\circ}C$ for 2 hr. Amylase, cellulase, and xylanase activities showed high values in extracts from P. ostreatus SMC, with 2.97 U/g, 1.67 U/g, and 91.56 U/g, respectively, whereas laccase activity and filter paper degradation ability were highest in extracts from P. eryngii SMC, with values of 9.01 U/g and 0.21 U/g, respectively. Enzymatic activities varied according to the SMCs released from different mushroom farms. The synthetic dyes remazol brilliant blue R and Congo red were decolorized completely by the SMC extract of P. eryngii within 120 min, and the decolorization ability of the extract was comparable to that of 0.3 U of commercial laccase. In addition, laccase activity of the SMC extract from P. eryngii was compared to that of commercial enzymes or its industrial application in decolorization.