• Title/Summary/Keyword: Fuel Vessel Design

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Prototype Product Based on the Functional Test of ANG Fuel Vessel Applied to Composite Carbon Fiber (탄소섬유 복합재료를 적용한 ANG 연료용기의 시제작 및 성능평가)

  • Kim, Gun-Hoi
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.18 no.3
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    • pp.7-13
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    • 2019
  • Recently, an automobile market used to natural gas has emerged as fast-growing as the several countries, who holds abundant natural fuel resources, has promoted to supply the national agency for an automobile car. LNG fuel vessel is more efficient in another way as the energy density is high, but it requires a high technology and investment to maintain extreme low temperature. CNG fuel vessel are relatively low-cost alternative to LNG, but poorly economical in terms of energy density as well as showing safety issues associated with compressed pressure. The development of adsorbed natural gas (ANG) has emerged as one of potential solutions. Therefore, it is desirable to reduce the weight of vessel by applying light-weighed a composite carbon fiber in order to response to the regulation of $CO_2$ emission. Herein, this study make the prototype ANG vessel not only based on the optimal design and analysis of material characteristic but also based on the shape design, and it suggest a new type for the composite carbon fiber vessel which verified functional test. Moreover, the detail shape design is analyzed by a finite element analysis, and its verifies the ANG vessel.

Design of Vessel Assembly for Fuel Irradiation Test in Reactor (원자로 내 핵연료조사시험용 압력용기조립체 설계)

  • Park, Kook-Nam;Lee, Jong-Min;Chi, Dae-Young;Park, Su-Ki;Lee, Chung-Young;Kim, Young-Jin
    • Proceedings of the KSME Conference
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    • 2004.11a
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    • pp.383-387
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    • 2004
  • The Fuel Test Loop (FTL) consists of In-Pile Test Section (IPS) and Out-of-Pile System (OPS). The test condition in IPS such as pressure, temperature and quality of the main cooling water, can be controlled by the OPS. The FTL has been developed to be able to irradiate three pins to the core irradiation hole (IR1 hole) by considering for its utility and user's irradiation requirement. The IPS vessel assembly (IVA) consists of IPS head, outer pressure vessel, inner pressure vessel, inner assembly and test fuel carrier. The IVA is approximately 5.6 m long and fits within a 74 mm in diameter envelope over the full height of the chimney. Above the top of the chimney, the head of the IPS is enlarged to allow the closure flanges and pipe work connections. IVA was designed to test the CANDU and PWR nuclear fuel pin together. Specially, wished to minimize interference by nuclear fuel change in design and synthesize these items and shape design for IVA.

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Optimal Shape Design of ANG Fuel Vessel Applied to Composite Carbon Fiber (탄소섬유 복합재료를 적용한 ANG 연료용기의 최적 형상설계)

  • Kim, Gun-Hoi
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.18 no.1
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    • pp.65-71
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    • 2019
  • The development of adsorbed natural gas (ANG) has emerged as one of potential solutions. It is desirable to reduce the weight of vessel by applying light-weighed a composite carbon fiber in order to response to a egulation of $CO_2$ emission. Through understanding of a composite carbon fiber, and material characteristic of a composite carbon fiber is required in order for better application of a reduction of weight and an analysis of material characteristic. Herein, this study suggest the composite carbon fiber vessel applied to the characteristic of carbon fiber, and it decides the preliminary shape based on the test of material characteristic for ANG vessel applied to a composite carbon fiber, and its basic shape calculate through on the netting theory. Moreover, the detail shape design is analyzed by a finite element analysis, and in the stage of detail sahp design and analysis of stress was performed on the typical shape using a finite element analysis, and the result of preliminary design was verified.

The Technology Development and Substantiation of Small Hydrogen Powered Vessel (소형 수소추진선박 기술 개발 및 실증 )

  • JAEWAN LIM;SEJUN LEE;SANGJIN YOON;OCKTAECK LIM
    • Transactions of the Korean hydrogen and new energy society
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    • v.34 no.6
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    • pp.555-561
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    • 2023
  • In this study, we proposed a standard model for the design, construction and demonstration of the technology development and substantiation of small hydrogen powered vessel in order to respond to the alternative fuel-using vessel market that requires the use of low-carbon/carbon-free fuel as a greenhouse gas reduction measure. The hydrogen fuel cell-based electric propulsion system developed through this is optimized through performance and durability tests on the land-based test site (LBTS), and the electric propulsion system applied to this result is mounted on a small hydrogen propulsion vessel and operated. Simultaneously, through the digital twin technology between the LBTS and the hydrogen-propelled vessel on the sea, the technology that can predict and diagnose the problems that can occur in the electric propulsion system of the vessel is applied to carry out the empirical study of the hydrogen-propelled vessel. In addition, we propose a commercialization model by analyzing the economic feasibility of the demonstration vessel.

On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor

  • Lim, Dong-Won;Lee, Cheol-Woo;Lim, Jae-Yong;Hartanto, Donny
    • Nuclear Engineering and Technology
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    • v.51 no.1
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    • pp.284-292
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    • 2019
  • For the continuous operation of a nuclear reactor, burnt fuel needs to be replaced with fresh fuel, where appropriate (ex-vessel) fuel handling is required. Particularly for the Sodium-cooled Fast Reactor (SFR) refueling, its process has unique challenges due to liquid sodium coolant. The ex-vessel spent fuel transportation should concern several design features such as the radiation shielding, decay-heat removal, and inert space separated from air. This paper proposes a new design optimization methodology of cask shielding to transport the spent fuel assembly in a prototype SFR for the first time. The Particle Swarm Optimization (PSO) algorithm had been applied to design trade-offs between shielding and cask weight. The cask is designed as a double-cylinder structure to block an inert sodium region from the air-cooling space. The PSO process yielded the optimum shielding thickness of 26 cm, considering the weight as well. To confirm the shielding performance, the radiation dose of spent fuel removed at its peak burnup and after 1-year cooling was calculated. Two different fuel positions located during transportation were also investigated to consider a functional disorder in a cask drive system. This study concludes the current cask design in normal operations is satisfactory in accordance with regulatory rules.

A Study on the Quantitative Risk Analysis Using CFD for the Fuel Gas Supply System of Gas Fueled Ship (가스추진선박의 가스연료공급시스템에 대한 CFD를 이용한 정량적 위험도 해석에 관한 연구)

  • Kim, Kipyoung;Kim, Daeheon;Lee, Youngho
    • Journal of the Society of Naval Architects of Korea
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    • v.54 no.1
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    • pp.1-9
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    • 2017
  • LNG has significant advantages in regard to environmental aspects comparing with conventional fuel oil. In fact, it is estimated that NOx and SOx emission can be reduced by about 90% and 100%, respectively in case of using LNG as a fuel. LNG-fuelled ship has been considered to be the best option both from an environmental and an economic point of view. Along with these trends, some major shipyards and Classification Societies have started to carry out the risk-based system design for LNG-fuelled ship such as passenger ship, platform supply vessel and large container vessel etc. However, new conceptual gas fuelled ship has high risk level compared with vessel using traditional crude oil especially in view of gas explosion accident. Therefore safety area where installed fuel gas supply system is required risk based system design with special considerations. On this paper, the entire process necessary for the quantitative risk analysis was explained to meet the satisfactory safety level of gas fuelled ship.

Analysis of Transportation and Handling system for Advanced spent fuel management process (사용후핵연료 차세대관리공정 운반취급계통 분석)

  • 홍동희;윤지섭;정재후;김영환;박병석;박기용;진재현
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2003.06a
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    • pp.1438-1441
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    • 2003
  • The project for "Development of Advanced Spent Fuel Management Technology" has a plan of a demonstration for the Advanced Management Process in the hot cell of IMEF. The Advanced Management Process are being developed for efficient and safe management of spent fuels. For the demonstration, several devices which are used to safely transport and handle nuclear materials without scattering have been derived by analyzing the Advanced Management Process, object nuclear material and modules of process equipment and performing graphical simulation of transportation/handling by computers. For verification, powder transportation vessel and handling device have been designed and manufactured. And several tests such as transporting, grappling, rotating the vessel have been performed. Also, the design requirements of transportation/handling equipment have been analyzed based on test results and process studies. The developed design requirements in this research will be used as the design data for the Advanced Management Process.

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Introduction For Market & Technical Trend of Regasification Vessel (Regasification vessel의 시장 전망과 기술 동향)

  • Lee, Dong-Hyun
    • Proceedings of the Korean Society of Marine Engineers Conference
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    • 2006.06a
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    • pp.181-182
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    • 2006
  • 최근 미주의 급격한 LNG 수요와 더불어 Safety, 환경 및 테러의 문제를 안고 있는 육상 LNG terminal의 대안으로 등장한 LNG Regasification Vessel의 시장 전망과 미주 지역의 엄격한 환경 규제를 만족시키기 위한 Regasification Vessel의 기술 동향에 대해 고찰하였다.

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The Effect of Seismic Level Increase on the Reactor Vessel Internals and Fuel Assemblies for the Korean Standard Suclear Power Plant (지진레벨의 증가가 한국표준형 원자력발전소의 원자로 내부구조물 및 핵연 료 집합체에 미치는 영향)

  • Jhung, M. J.
    • Journal of KSNVE
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    • v.7 no.1
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    • pp.33-41
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    • 1997
  • To cover a range of possible site conditions where the Korean standard nuclear power plant may be constructed, a range of generic site conditions is selected for geologic and seismologic evaluation. To envelop other Asian countries as well as the Korean peninsula, there is an attempt to increase the seismic level to 0.3g ground motions for the safe shutdown earthquake. The dynamic analyses of the reactor vessel internals and fuel assemblies are performed for the increased motions and the effect of seismic level on the response is investigated. Also the nonlinear response characteristics are discussed by comparing the loads between operating basis earthquake and safe shutdown earthquake excitations. The design adequacy of the reactor vessel internals and fuel assemblies for the increased seismic level is addressed.

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