• Title/Summary/Keyword: research vessel

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A Study on the Prediction of Welding Distortion of Vacuum Vessel during Fabrication Process (진공 용기 제작시 공정별 변형 예측에 관한 연구)

  • Lee, Dong-Ju;Kim, Ha-Geun;Shin, Sang-Beom
    • Proceedings of the KWS Conference
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    • 2009.11a
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    • pp.96-96
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    • 2009
  • The purpose of this study is to clarify the transitional behavior and main factor of excessive welding distortion caused by fabrication process of STS 304 vacuum vessel having double curvature for the efficient quality control of vacuum vessel. In order to do it, the predictive equations of the welding distortion in simple weldment of vacuum vessel were established by conventional finite element analysis. And the principal factor controlling the welding distortion was identified by evaluating the welding distortion of vacuum vessel in each fabrication process with FEA and simplified thermo elastic method. Based on the results, the principal factors of distortion of vacuum vessel were clarified as angular distortion and transverse shrinkage which are a source of excessive out-of plane distortion in the double curved vacuum vessel. It was expected that the FE analysis results of this study could contribute to establish the proper control method of welding distortion for double curved vacuum vessel.

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Hull Form and Layouts of 740-ton Replacement Vessel for R/V Eardo of KIOST: Ship Design and SMRs (740톤급 종합해양연구선 이어도호 대체선 선형 및 설계 특성)

  • Park, Cheong Kee;Park, Dong-Won;Lee, Gun Chang;Kim, Young Jun;Min, Young Ki
    • Ocean and Polar Research
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    • v.42 no.2
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    • pp.171-178
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    • 2020
  • R/V EARDO, commissioned in 1992, has successfully carried out ocean research campaigns in Korean jurisdictional and adjacent waters, including continental margins and coastal zones within the Korean Exclusive Economic Zone (EEZ), for 29 years. However, it will soon be reaching the end of its useful service life. A replacement for R/V EARDO is urgently needed to ensure the safety of vessel itself and its crews, and efficient ship operation and maintenance, as well as to meet modern scientific mission requirements (SMRs). Basic specifications for a replacement ship have been devised and reviewed over the past nine months. A test of the proposed hull form was also performed. The total tonnage of the proposed vessel is approximately 740 tons, and the overall length and width are 62.0 and 11.6 m, respectively. The new ship will thus be 73% larger than the current R/V EARDO; in particular, the research workspace will be 4.4 times larger. The major design priorities are the propulsion system, efficiency of radiated noise and vibration control, and the dynamic positioning system. An environmentally friendly emission system, meeting International Maritime Organization (IMO) Tier III regulations, will be installed in the third exhaust pipe. Various wet and dry lab spaces as well as 32 different scientific instruments have also been considered in the ship design.

Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART

  • Sang Ho Kim;Jaehyun Ham;Byeonghee Lee;Sung Il Kim;Hwan Yeol Kim;Rae-Joon Park;Jaehoon Jung
    • Nuclear Engineering and Technology
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    • v.54 no.12
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    • pp.4551-4559
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    • 2022
  • The aim of this research is to analyze the characteristics of a core melt discharged from the reactor vessel and the spreading behavior the core melt in the reactor cavity of the SMART. First, a severe accident sequence under conservative conditions is simulated by the MELCOR code to obtain the conditions for an analysis of the spreading behavior and coolability of the ex-vessel melt. Second, the spreading behavior and coolability of the ex-vessel melt are analyzed by the MELTSPREAD code. The level, temperature, and pressure of the water in the cavity as well as the temperature, mass, composition, and discharge velocity of the melt were utilized to construct the ex-vessel analysis. The melt spread only to part of the cavity, and that the height of the corium in a static state was less than 25 cm. The characteristics of a small modular reactor on the spreading behavior and coolability of melt were analyzed. In the SMART, the amount of melt discharged into the cavity is relatively small and the area of the cavity is sufficiently large when compared to a high-power pressurized water reactor. It was found that the coolability of an ex-vessel core melt can be sufficiently secured.

Operating performance of squid jigging vessel using the LED and metal halide fishing lamp combination (LED와 메탈핼라이드 집어등을 겸용한 오징어채낚기 어선의 조업 성능)

  • An, Heui-Chun;Bae, Jae-Hyun;Bae, Bong-Seong;Park, Jong-Myung
    • Journal of the Korean Society of Fisheries and Ocean Technology
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    • v.49 no.4
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    • pp.395-403
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    • 2013
  • Fishing efficiency of the squid jigging vessel using the LED and metal halide fishing lamp combination was analyzed to reduce the cost for fishing operation utilizing the fishing light system for high degree of efficiency in the squid jigging fishery (one of the representative coastal and offshore fisheries in Korea). This study aims to improve the nature of existing LED lamps and to develop fan-shaped LED lights having 180W of power and ${\pm}45^{\circ}$ angle of light intensity distribution. The marine experiment for making a comparison of their fishing efficiency was tested by a 9.77 tons fishing vessel from Oct. through Dec. 2012. As a result, experimental fishing vessel showed slightly higher fishing efficiency than the average of metal halide lamp-equipped vessel and 20% energy savings. This means that the combination of LED and metal halide lamps would provide an efficient way to lower energy consumption while maintaining fishing efficiency.

Affiliated Coordination of Rescue and Salvage in ASEAN+3

  • Yoon, Dae-Gwun
    • Journal of Navigation and Port Research
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    • v.33 no.2
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    • pp.111-117
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    • 2009
  • On May 12th, 2007 a merchant vessel of Golden Rose (South Korea) sank into near 38 mile from Yentai in China after the vessel collided with a container vessel of Jinsung (China), leaving all 16 sailors, including seven South Koreans, missing. According to the official report. The Chinese vessel, authorities, and South Korean government did not coordination q rescue and salvage for the sailors and vessel properly as follows: 1) The Chinese vessel left the scene without rescue and salvage of the sailors, 2) Chinese authorities failed to comply with law of the sea that required them to report the collision to South Korea immediately after confirming the accident, and 3) The South Korean government is also being criticized for its slow response to the incident since the government did not set up a response team until 21 hours after the incident. In order to reduce this number of sailor missing in future incidents, this research is studied regarding assembling conferences, assigning SRR in ASEAN+3, simplicity to enter other territory waters and cooperative training and education for the SAR.

The assessment of Safe Navigation Regarding Hydrodynamic forces between ships in Restricted Waterways

  • Lee, Chun-Ki;Yoon, Jeom-Dong
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • v.1
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    • pp.89-93
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    • 2006
  • This paper is primarily focused on the safe navigation between overtaking and overtaken vessels in restricted waterways under the external forces, such as wind and current. The maneuvering simulation between two ships was conducted to find an appropriate safe speed and distance, which is required to avoid collision. From the viewpoint of marine safety, a greater transverse distance between two ships is more needed for the smaller vessel. Regardless of external forces, the smaller vessel will get a greater effect of hydrodynamic forces than the bigger one. In the case of close navigation between ships under the forces of wind and current, the vessel moving at a lower speed is potentially hazardous because the rudder force of the lower speed vessel is not sufficient for steady-state course-keeping, compared to that of the higher speed vessel.

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Steady-State Performance Analysis of Pressurizer and Helical Steam Generator for SMART

  • Seo, Jae-Kwang;Kang, Hyung-Seok;Kim, Hwan-Yeol;Cho, Bong-Hyun;Lee, Doo-Jeong
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.310-315
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    • 1997
  • System-Integrated Modular Advanced Reactor (SMART), where major primary components such as modular helical steam generator and self regulating pressurizer are integrated into reactor vessel, is currently under development. The pressurizer is designed to control the primary pressure mainly with partial pressure of nitrogen gas and to maintain the fluid temperature as low as possible for the purpose of minimizing steam contribution. The steam generator (SG) is designed to produce super-heated steam inside tube at power operation. Because the in-vessel pressurizer and in-vessel SG are classified as the characteristic components of SMART, it is important to perform a steady state calculation of these components in order to evaluate the adoption of these components. A steady state analysis of the in-vessel pressurizer and in-vessel SG has been performed under normal power operation and the results show an acceptable performance of the components.

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THERMAL AND STRUCTURAL ANALYSIS OF CALANDRIA VESSEL OF A PHWR DURING A SEVERE ACCIDENT

  • Kulkarni, P.P.;Prasad, S.V.;Nayak, A.K.;Vijayan, P.K.
    • Nuclear Engineering and Technology
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    • v.45 no.4
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    • pp.469-476
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    • 2013
  • In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may lead to the collapse of pressure tubes and calandria tubes, which may ultimately relocate inside the calandria vessel forming a terminal debris bed. The debris bed, which may reach high temperatures due to the decay heat, is cooled by the moderator in the calandria. With time, the moderator is evaporated and after some time, a hot dry debris bed is formed. The debris bed transfers heat to the calandria vault water which acts as the ultimate heat sink. However, the questions remain: how long would the vault water be an ultimate heat sink, and what would be the failure mode of the calandria vessel if the heat sink capability of the reactor vault water is lost? In the present study, a numerical analysis is performed to evaluate the thermal loads and the stresses in the calandria vessel following the above accident scenario. The heat transfer from the molten corium pool to the surrounding is assumed to be by a combination of radiation, conduction, and convection from the calandria vessel wall to the vault water. From the temperature distribution in the vessel wall, the transient thermal loads have been evaluated. The strain rate and the vessel failure have been evaluated for the above scenario.

Enhancement of Downward-Facing Saturated Boiling Heat Transfer by the Cold Spray Technique

  • Sohag, Faruk A.;Beck, Faith R.;Mohanta, Lokanath;Cheung, Fan-Bill;Segall, Albert E.;Eden, Timothy J.;Potter, John K.
    • Nuclear Engineering and Technology
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    • v.49 no.1
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    • pp.124-133
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    • 2017
  • In-vessel retention by passive external reactor vessel cooling under severe accident conditions is a viable approach for retention of radioactive core melt within the reactor vessel. In this study, a new and versatile coating technique known as "cold spray" that can readily be applied to operating and advanced reactors was developed to form a microporous coating on the outer surface of a simulated reactor lower head. Quenching experiments were performed under simulated in-vessel retention by passive external reactor vessel cooling conditions using test vessels with and without cold spray coatings. Quantitative measurements show that for all angular locations on the vessel outer surface, the local critical heat flux (CHF) values for the coated vessel were consistently higher than the corresponding CHF values for the bare vessel. However, it was also observed for both coated and uncoated surfaces that the local rate of boiling and local CHF limit vary appreciably along the outer surface of the test vessel. Nonetheless, results of this intriguing study clearly show that the use of cold spray coatings could enhance the local CHF limit for downward-facing boiling by > 88%.

An Investigation of Thermal Margin for External Reactor Vessel Cooling(ERVC) in Large Advanced Light Water Reactors(ALWR)

  • Park, Jong-Woon;Jerng, Dong-Wook
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.473-478
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    • 1997
  • A severe accident management strategy, in-vessel retention corium through external reactor vessel cooling(ERVC) is being studied worldwide as a means to prevent reactor vessel failure following a core melt accident. An evaluation of feasibility of this ERVC for a large Advanced Light Water Reactor (ALWR) is presented. To account for the coolability of corium and metal in the reactor vessel, a thermal analysis is performed using an existing method. Results show that the peak heat flux along the inner surface of the reactor vessel lower head has a relatively smaller margin than a small capacity reactor such as AP600 in regards with the critical heat flux attainable at the outer surface of the reactor vessel lower head.

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