• Title/Summary/Keyword: Energy & fuel technology

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Study for Failure Examples of Solenoid Valve, Relay and Idle Speed Control Actuator in Liquid Petroleum Gas vehicle Engines (LPG 자동차 엔진의 솔레노이드밸브, 릴레이, 공회전조절장치의 고장사례 연구)

  • Kim, Chung-Kyun;Lee, Il-Kwon;Cho, Seung-Hyun
    • Journal of the Korean Institute of Gas
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    • v.15 no.3
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    • pp.47-52
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    • 2011
  • The purpose of this paper analyzes and studies to seek the failure examples of electronic control actuators for engine in liquified petroleum gas vehicle. The first, it was verified phenomenon for intial starting damage and no-acceleration of engine because of occasionally fuel feeding interception by clogged of emergency cutting solenoid valve filter. The second, the contact resistance produced in the connecting part of engine control relay because of no fully surface contacting by processes and assembly badness. It was displayed phenomenon of re-starting badness. The actuator that idle speed control system was sticked inside because of intake-air decreasing by carbon deposit. As a result, it was verified the phenomenon of disharmony that repeated up and down the engine revolution.

On the Weight Reduction of Longitudinal Members of Mid-Sized Bulk Carrier Considering the Minimum Shear Force according to Compartment Arrangement based on H-CSR (구획배치에 따른 최소 전단력을 고려한 H-CSR 기반 중형 살물선 종강도 부재의 중량 절감 방안 연구)

  • Na, Seung-Soo;Song, Ha-Cheol;Jeong, Sol;Park, Min-Cheol;Bae, Sang-Don
    • Journal of the Society of Naval Architects of Korea
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    • v.54 no.4
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    • pp.352-359
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    • 2017
  • Because the Energy Efficiency Design Index(EEDI) came into effect in 2013, it is necessary to develop a new technology to overcome $CO_2$ emission regulations. In structural design viewpoint, lots of researches are carried out to develop eco-friendly and high fuel efficiency ships by weight reduction. By using the automated compartment arrangement system and automated structural design algorithm which were developed by the authors, new researches are performing to combine the above two systems. However, the effect of weight reduction was not significant because structural designs by using these systems for the midship part was carried out only focused on the minimum still water bending moment. In this paper, at first, good compartment arrangements which give the minimum still water bending moment and(or) shear force were chosen by using the automated compartment system. And then, influence of shear force on weight reduction was investigated by using the automated structural design algorithm considering longitudinal strength, local strength and shear strength of longitudinal members in cargo holds. Conclusively, it is necessary to consider the minimum still water bending moment and shear force simultaneously to reduce the weight of mid-sized bulk carrier. Also, good compartment arrangement which gives much more weight reduction compared with existing ship was proposed.

Analytical Solutions for a Three-Member Decay Chain of Radionuclides Transport in a Single Fractured Porous Rock (단일균열 다공성암반에서 방사성핵종의 수송에 대한 3단계 붕괴사슬의 해석해)

  • Yu, Young-Woo;Chung, Chang-Hyun;Kim, Chang-Lak
    • Nuclear Engineering and Technology
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    • v.26 no.4
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    • pp.453-460
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    • 1994
  • The migration equation is modified for a three-member decay chain in the fracture and porous matrix Analytical solutions are obtained by utilizing Laplace transform the initial conditions of Delta function and Bateman equation. The concentrations for each nuclide of Np$^{237}$ -U$^{233}$ -Th$^{229}$ and U$^{234}$ -Th$^{230}$ -Ra$^{226}$ chains selected from the 4n+1 and 4n+2 chains are plotted by utilizing analytical solutions in the fracture. Retardation coefficient of the nuclides are obtained using those of the granite. The results indicate that the daughter nuclides such as U$^{233}$ , Th$^{229}$ , Th$^{230}$ and Ra$^{226}$ become important at the far field from the repository though there is very small initial inventory in the waste solid or spent fuel, for they are produced by the mother nuclides decayed in the fracture and porous matrix.

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The conversion of ammonium uranate prepared via sol-gel synthesis into uranium oxides

  • Schreinemachers, Christian;Leinders, Gregory;Modolo, Giuseppe;Verwerft, Marc;Binnemans, Koen;Cardinaels, Thomas
    • Nuclear Engineering and Technology
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    • v.52 no.5
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    • pp.1013-1021
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    • 2020
  • A combination of simultaneous thermal analysis, evolved gas analysis and non-ambient XRD techniques was used to characterise and investigate the conversion reactions of ammonium uranates into uranium oxides. Two solid phases of the ternary system NH3 - UO3 - H2O were synthesised under specified conditions. Microspheres prepared by the sol-gel method via internal gelation were identified as 3UO3·2NH3·4H2O, whereas the product of a typical ammonium diuranate precipitation reaction was associated to the composition 3UO3·NH3·5H2O. The thermal decomposition profile of both compounds in air feature distinct reaction steps towards the conversion to U3O8, owing to the successive release of water and ammonia molecules. Both compounds are converted into α-U3O8 above 550 ℃, but the crystallographic transition occurs differently. In compound 3UO3·NH3·5H2O (ADU) the transformation occurs via the crystalline β-UO3 phase, whereas in compound 3UO3·2NH3·4H2O (microspheres) an amorphous UO3 intermediate was observed. The new insights obtained on these uranate systems improve the information base for designing and synthesising minor actinide-containing target materials in future applications.

A Study on the Pelletization of Powdered Radioactive Waste by Roll Compaction (롤 컴팩션을 이용한 분말 방사성폐기물의 펠렛화 연구)

  • Song, Jong-Soon;Lim, Sang-Hyun;Jung, Min-Young;Kim, Ki-Hong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.2
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    • pp.203-212
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    • 2019
  • Disposal nonconformity of radioactive wastes refers to radioactive wastes that need to be treated, solidified and packaged during operation or decommissioning of NPPs, and are typically exemplified by particulate radioactive wastes with dispersion characteristics. These wastes include the dried powders of concentrated wastes generated in the process of operating NPPs, slurry and sludge, various powdered wastes generated in the decommissioning process (crushed concrete, decontamination sludge, etc.), and fine radioactive soil, which is not easy to decontaminate. As these particulate wastes must be packaged so that they become non-dispersive, they are solidified with solidification agents such as cement and polymer. If they are treated using existing solidification methods, however, the volume of the final wastes will increase. This drawback may increase the disposal cost and reduce the acceptability of disposal sites. Accordingly, to solve these problems, this study investigates the pelletization of particulate radioactive wastes in order to reduce final waste volume.

A Study on the Integration of Motor - Transmission for Commercial Electric Vehicle (상용전기자동차용 모터-변속기 일체화에 관한 연구)

  • Oh, Se-Hoon;Youm, Kwang-Wook
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.20 no.6
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    • pp.306-313
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    • 2019
  • Owing to the present problems of air pollution and fossil fuel exhaustion, ongoing research has been actively focused on developing an electric actuator system that can utilize diverse energy sources without producing any exhaust gas. Since the motors of such electric vehicles generally rotate at a high speed, the initial acceleration capability required for an automobile is insufficient. In this study, the motor output was decelerated by the transmission; the initial acceleration of the vehicle was increased, and the motor size and weight were reduced. The driving motor and transmission, which each form isolated structures, were integrated to simplify the connector for input and output. By reducing the cooling system's capacity, a vehicle was designed and manufactured that represents a structural change in effective technology.

A Study on Annual Release Objectives and Annual Release Limits of Gaseous Effluents During Decommissioning of Nuclear Power Plants (원전 해체 시 기체상 유출물의 연간 방출관리치 및 방출한도치에 관한 연구)

  • Lee, Seung-Hee;Hwang, Won-Tae;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.3
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    • pp.299-311
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    • 2019
  • Decommissioning is a critical issue in Korea. Although compared with the operation of nuclear power plants the release of radioactive materials during decommissioning is not expected to be significant, residents should always be protected from radiation exposure. To manage this effectively, Annual Release Objectives (ARO) and Annual Release Limits (ARL) were derived from dose standards in the NSSC Notice and dose limit for the public. Based on meteorological data for the three years from 2008 to 2010 in the Shin Kori nuclear power plant site, atmospheric dispersion and ground deposition factors of gaseous effluent were evaluated using the XOQDOQ computer code. The exposure dose was evaluated using the ENDOS-G computer code. Because of differences in radiological sensitivity according to age groups, the results of Annual Release Objectives (ARO) and Annual Release Limits (ARL) showed significant differences depending on the radionuclides. The evaluation methodology of this study will provide meaningful information for radioactive effluent management for decommissioning of nuclear power plants.

Stress Singularity Behaviour in the Frictional Complete Contact Problem of Three Bodies (세 물체 간 마찰 완전 접촉 문제의 응력 특이성 거동)

  • Kim, Hyung-Kyu
    • Tribology and Lubricants
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    • v.35 no.4
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    • pp.229-236
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    • 2019
  • This study investigates the stress singularity that occurs at the contact edge of three bodies in a frictional complete contact. We use the asymptotic analysis method, wherein we constitute an eigenvalue problem and observe the eigenvalue behavior, which we use to obtain the order of the stress singularity. For the present geometry of three bodies in contact, a contact between a cracked indenter and half plane is considered. This is a typical geometry of the PCMI problem of a nuclear fuel rod. Thus, this paper, specifically presents the characteristics of the PCMI problem from the perspective of stress singularity. Consequently, it is noted that the behavior of the stress singularity varies with the difference in the crack angle, coefficient of friction, and material dissimilarity, as is observed in a frictional complete contact of two bodies. In addition, we find that the stress singularity changes essentially linearly with respect to the coefficient of friction, regardless of the variation in the crack angle and material dissimilarity. Concurrently, we find the order of singularity to be 0.5 at a certain coefficient of friction, irrespective of the crack angle, which we also observe in the crack problem of a homogeneous and isotropic body. The order of singularity can also exceed 0.5 in the frictional complete contact problem of three bodies. This implies that the propensity for failure when three bodies are in frictional complete contact can be even worse than that in case of a failure induced by a crack.

Suggestion of Risk Assessment Methodology for Decommissioning of Nuclear Power Plant (원자력발전소 해체 위험도 평가 방법론 개발)

  • Park, ByeongIk;Kim, JuYoul;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.1
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    • pp.95-106
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    • 2019
  • The decommissioning of nuclear power plants should be prepared by quantitative and qualitative risk assessment. Radiological and non-radiological hazards arising during decommissioning activities must be assessed to ensure the safety of decommissioning workers and the public. Decommissioning experiences by U.S. operators have mainly focused on deterministic risk assessment, which is standardized by the U.S. Nuclear Regulatory commission (NRC) and focuses only on the consequences of risk. However, the International Atomic Energy Agency (IAEA) has suggested an alternative to the deterministic approach, called the risk matrix technique. The risk matrix technique considers both the consequence and likelihood of risk. In this study, decommissioning stages, processes, and activities are organized under a work breakdown structure. Potential accidents in the decommissioning process of NPPs are analyzed using the composite risk matrix to assess both radiological and non-radiological hazards. The levels of risk for all potential accidents considered by U.S. NPP operators who have performed decommissioning were estimated based on their consequences and likelihood of events.

A Study on Water-Proof Characteristics of a Stainless Steel Mesh by Electrochemical Etching Process (전기화학 에칭 공정을 이용한 스테인리스 스틸 메쉬의 방수 특성 연구)

  • Lee, Chan;Kim, Ji Min;Kim, Hyungmo
    • Tribology and Lubricants
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    • v.37 no.5
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    • pp.189-194
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    • 2021
  • A straightforward, yet effective surface modification method of stainless steel mesh and its interesting anti-wetting characteristics are reported in this study. The stainless steel mesh is electrochemically etched, and the specimen has both micro and nano-scale structures on its surface. This process transforms the two types of mesh specimens known as the regular and dense specimens into hydrophobic specimens without applying any hydrophobic chemical coating process. The fundamental wettability of the modified mesh is analyzed through a dedicatedly designed experiment to investigate the waterproof characteristics, for instance, the penetration threshold. The waterproof characteristics are evaluated in a manner that the modified mesh resists as high as approximately 2.7 times the pressure compared with the bare mesh, i.e., the non-modified mesh. The results show that the penetration threshold depends primarily on the advancing contact angles, and the penetration stop behaviors are affected by the contact angle hysteresis on the surfaces. The findings further confirm that the inexpensive waterproof meshes created using the proposed straightforward electrochemical etching process are effective and can be adapted along with appropriate designs for various practical applications, such as underwater devices, passive valves, and transducers. In general, , additional chemical coatings are applied using hydrophobic materials on the surfaces for the applications that require water-repelling capabilities. Although these chemical coatings can often cause aging, the process proposed in this study is not only cost-effective, but also durable implying that it does not lose its waterproof properties over time.