• Title/Summary/Keyword: High-technology facility

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Characteristics of Cyclone and Electric Dust Collection Oil Filters for Selective Removal of Fiber Tenter Air Pollutants (섬유 텐터 대기오염물질의 선택적 제거를 위한 싸이클론 및 전기 집진 오일필터의 특성)

  • Jin Ho Jung;Seung Hwan Ryu;Soon Duk Kwon;Yoon Hyun Cho
    • Textile Coloration and Finishing
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    • v.35 no.4
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    • pp.256-273
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    • 2023
  • Among the dyeing industries, the tenter process is a process that improves the quality of fibers by drying and ironing (heat treatment) dyed fabrics, and drugs such as water repellents, antistatic agents, and fiber softeners are mainly used in these tenter processes. These drugs are vaporized in the process of treatment by high temperatures (180 ~ 230℃), and are observed in a complex form such as white smoke, oil mist, and fine dust, causing odor. To treat the complex exhaust gas at the rear end of the tenter facility, most companies operate by installing a wet scrubber and an adsorption tower alone or in parallel, but there are many problems. In particular, the insoluble oil mist at the rear end of the tenter has significantly low processing efficiency in the cleaning dust collection facility, and there is a problem in the facility by adsorption due to the occlusion phenomenon caused by the oil mist. In addition, the odor gas at the rear end of the tenter contains a lot of aldehydes, and in order to improve these various problems, a complex exhaust purification device using cyclone and electric support collector was developed. This study examined the applicability of economical and efficient technology by removing complex air pollution at the rear end of the tenter and applying improved technology than the existing technology.

Mock-up Test for Nuclear Power Plant Rebar Modulation Applying Febrication (선조립공법을 활용한 원전구조물 철근모듈화 Mock-up 실험연구)

  • Lim, Sang-Jun;Lee, Byung-Soo
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2015.05a
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    • pp.13-14
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    • 2015
  • To minimize construction of nuclear facility, it is required to reduce reinforcing bar amount and solve reinforcing bar concentration and for this, it is necessary to develop appication design technology and modular of high strength reinforcing bar. Hence, KHNP reduces excessive reinforcing bar amount which can cause possibility of poor construction of concrete through design standard development and modular of nuclear facility structure using high strength reinforcing bar to raise economics and has its purpose to maintain high-level safety and durability as they are. After reviewing the rebar drawing of the NPP structures and performing the mock-up test, the rebar modulation method in the various area of the NPP Structure has been established.

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Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux

  • Bedenko, Sergey V.;Arzhannikov, Andrey V.;Lutsik, Igor O.;Prikhodko, Vadim V.;Shmakov, Vladimir M.;Modestov, Dmitry G.;Karengin, Alexander G.;Shamanin, Igor V.
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.1736-1746
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    • 2021
  • The results of full-scale numerical experiments of a hybrid thorium-containing fuel cell facility operating in a close-to-critical state due to a controlled source of fusion neutrons are discussed in this work. The facility under study was a complex consisting of two blocks. The first block was based on the concept of a high-temperature gas-cooled thorium reactor core. The second block was an axially symmetrical extended plasma generator of additional neutrons that was placed in the near-axial zone of the facility blanket. The calculated models of the blanket and the plasma generator of D-T neutrons created within the work allowed for research of the neutronic parameters of the facility in stationary and pulse-periodic operation modes. This research will make it possible to construct a safe facility and investigate the properties of thorium fuel, which can be continuously used in the epithermal spectrum of the considered hybrid fusion-fission reactor.

Design and fabrication of beam dumps at the µSR facility of RAON for high-energy proton absorption

  • Jae Chang Kim;Jae Young Jeong;Kihong Pak;Yong Hyun Kim;Junesic Park;Ju Hahn Lee;Yong Kyun Kim
    • Nuclear Engineering and Technology
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    • v.55 no.10
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    • pp.3692-3699
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    • 2023
  • The Rare isotope Accelerator complex for ON-line experiments in Korea houses several accelerator complexes. Among them, the µSR facility will be initially equipped with a 600 MeV and 100 kW proton beam to generate surface muons, and will be upgraded to 400 kW with the same energy. Accelerated proton beams lose approximately 20% of the power at the target, and the remaining power is concentrated in the beam direction. Therefore, to ensure safe operation of the facility, concentrated protons must be distributed and absorbed at the beam dump. Additionally, effective dose levels must be lower than the legal standard, and the beam dumps used at 100 kW should be reused at 400 kW to minimize the generation of radioactive waste. In this study, we introduce a tailored method for designing beam dumps based on the characteristics of the µSR facility. To optimize the geometry, the absorbed power and effective dose were calculated using the MCNP6 code. The temperature and stress were determined using the ANSYS Mechanical code. Thus, the beam dump design consists of six structures when operated at 100 kW, and a 400 kW beam dump consisting of 24 structures was developed by reusing the 100 kW beam dump.

Failure Evaluation Plan of a Reactor Internal Components of a Decommissioned Plant

  • Hwang, Seong Sik;Kim, Sung Woo;Choi, Min Jae;Cho, Sung Hwan;Kim, Dong Jin
    • Corrosion Science and Technology
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    • v.20 no.4
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    • pp.189-195
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    • 2021
  • A technology for designing and licensing a dedicated radiation shielding facility needs to be developed for safe and efficient operation an R&D center. Technology development is important for smooth operation of such facilities. Causes of damage to internal structures (such as baffle former bolt (BFB) of pressurized water reactor) of a nuclear power reactor should be analyzed along with prevention and countermeasures for similar cases of other plants. It is important to develop technologies that can comprehensively analyze various characteristics of internal structures of long term operated reactors. In high-temperature, high-pressure operating environment of nuclear power plants, cases of BFB cracks caused by irradiated assisted stress corrosion cracks (IASCC) have been reported overseas. The integrity of a reactor's internal structure has emerged as an important issue. Identifying the cause of the defect is requested by the Korean regulatory agency. It is also important to secure a foundation for testing technology to demonstrate the operating environment for medium-level irradiated testing materials. The demonstration testing facility can be used for research on material utilization of the plant, which might have highest fluence on the internal structure of a reactor globally.

Secure Data Transmission Scheme between Network for Building Facilities Control System (빌딩시설 제어시스템용 안전한 망간 자료전송 방안)

  • Jo, In-June
    • The Journal of the Korea Contents Association
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    • v.18 no.8
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    • pp.102-108
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    • 2018
  • The existing data transmission technology applied between the non-secure external internet and the secure internal business network has various problems when applied to the building facility management SCADA system control network. Traditional inter-network data transfer technologies involve high complexity and high costs because blacklist-based security techniques are applied to all data. However, whitelist-based security techniques can be applied to data distributed in Building Facility Management SCADA control systems because a small number of structured control data are repeatable and periodic. This simplifies the security technology applied to inter-network data transmission, enabling building facility management SCADA system control network deployment at low cost. In this paper, we proposed building control networks specialized in building facility management SCADA control systems by providing solutions to address and address these problems.

E-Isolation : High-performance Dynamic Testing Installation for Seismic Isolation Bearings and Damping Devices

  • Yoshikazu Takahashi;Toru Takeuchi;Shoichi Kishiki;Yozo Shinozaki;Masako Yoneda;Koichi Kajiwara;Akira Wada
    • International Journal of High-Rise Buildings
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    • v.12 no.1
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    • pp.93-105
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    • 2023
  • Seismic isolation and vibration control techniques have been developed and put into practical use by challenging researchers and engineers worldwide since the latter half of the 20th century, and after more than 40 years, they are now used in thousands of buildings, private residences, highways in many seismic areas in the world. Seismic isolation and vibration control structures can keep the structures undamaged even in a major earthquake and realize continuous occupancy. This performance has come to be recognized not only by engineers but also by ordinary people, becoming indispensable for the formation of a resilient society. However, the dynamic characteristics of seismically isolated bearings, the key elements, are highly dependent on the size effect and rate-of-loading, especially under extreme loading conditions. Therefore, confirming the actual properties and performance of these bearings with full-scale specimens under prescribed dynamic loading protocols is essential. The number of testing facilities with such capacity is still limited and even though the existing labs in the US, China, Taiwan, Italy, etc. are conducting these tests, their dynamic loading test setups are subjected to friction generated by the large vertical loads and inertial force of the heavy table which affect the accuracy of measured forces. To solve this problem, the authors have proposed a direct reaction force measuring system that can eliminate the effects of friction and inertia forces, and a seismic isolation testing facility with the proposed system (E-isolation) will be completed on March 2023 in Japan. This test facility is designed to conduct not only dynamic loading tests of seismic isolation bearings and dampers but also to perform hybrid simulations of seismically isolated structures. In this paper, design details and the realization of this system into an actual dynamic testing facility are presented and the outcomes are discussed.

의약품 제조시설의 포름알데히드가스 훈증살균과 최근 실내무균화방법의 동향

  • 한국공기청정협회
    • Air Cleaning Technology
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    • v.23 no.3
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    • pp.34-43
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    • 2010
  • In most productive facility of pharmaceutical companies, the fumigation using formaldehyde gas has been put into operation. Because formaldehyde gas is so bactericidal as to sterilize bacterial spore which can not be sterilized with usual disinfectants, it has been used for fumigation in many facilities such as facility of experimental animals, research institute and productive facility of pharmaceutical companies which are required to be high level of biological clean. However, the use of formaldehyde is recently under the strict management because of its causing of sick house and carcinogenesis. We introduce the conditions of sterilization using formaldehyde gas, the examples of sterilization using formaldehyde gas in a pharmaceutical manufacture and the problems of use of formaldehyde against environments and health. Further, we describe the characteristics and future subjects of the sterilization method using gasified oxidants such as hydrogen peroxide, peracetic acid and chlorine oxide.

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Thermal-hydraulic behavior simulations of the reactor cavity cooling system (RCCS) experimental facility using Flownex

  • Marcos S. Sena;Yassin A. Hassan
    • Nuclear Engineering and Technology
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    • v.55 no.9
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    • pp.3320-3325
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    • 2023
  • The scaled water-cooled Reactor Cavity Cooling System (RCCS) experimental facility reproduces a passive safety feature to be implemented in Generation IV nuclear reactors. It keeps the reactor cavity and other internal structures in operational conditions by removing heat leakage from the reactor pressure vessel. The present work uses Flownex one-dimensional thermal-fluid code to model the facility and predict the experimental thermal-hydraulic behavior. Two representative steady-state cases defined by the bulk volumetric flow rate are simulated (Re = 2,409 and Re = 11,524). Results of the cavity outlet temperature, risers' temperature profile, and volumetric flow split in the cooling panel are also compared with the experimental data and RELAP system code simulations. The comparisons are in reasonable agreement with the previous studies, demonstrating the ability of Flownex to simulate the RCCS behavior. It is found that the low Re case of 2,409, temperature and flow split are evenly distributed across the risers. On the contrary, there's an asymmetry trend in both temperature and flow split distributions for the high Re case of 11,524.

Parametric Study for Structural Reinforcement Methods of Disposal Container for NPP Decommissioning Radioactive Waste

  • Hyungoo Kang;Hoseog Dho;Jongmin Lim;Yeseul Cho;Chunhyung Cho
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.21 no.3
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    • pp.329-345
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    • 2023
  • This paper described a method for analyzing the structural performance of a metal container used for disposing radioactive waste generated during the decommissioning of a nuclear power plant, and numerical analysis results of a method for reinforcing the container. The containers to be analyzed were those that can be used in near-surface and landfill disposal facilities scheduled to be operated at the Gyeongju radioactive waste disposal facility. Structural reinforcement of the container was performed by lattice reinforcement, column reinforcement, and bottom plate reinforcement. Accordingly, a total of 14 reinforcement cases were modeled. The external force causing damage to the container was set equivalent to the impact of a 9-m fall, accounting for the height of the vault at the near-surface disposal facility. The reinforcement methods with a high contribution to the structural performance of the container were concluded to be lattice and column reinforcements.