• Title, Summary, Keyword: Transport Vessel

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Neutron Fluence Evaluation for Reactor Pressure Vessel Using 3D Discrete Ordinates Transport Code RAPTOR-M3G (3차원 수송계산 코드(RAPTOR-M3G)를 이용한 원자로 압력용기 중성자 조사량 평가)

  • Maeng, Young Jae;Lim, Mi Joung;Kim, Byoung Chul
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.10 no.1
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    • pp.107-112
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    • 2014
  • The Code of Federal Regulations, Title 10, Part 50, Appendix H requires surveillance program for reactor pressure vessel(RPV) that the peak neutron fluence at the end of the design life of the vessel will exceed $1.0E+17n/cm^2$ (E>1.0MeV). 2D/1D Synthesis method based on DORT 3.1 transport calculation code has been widely used to determine fast neutron(E>1.0MeV) fluence exposure to RPV in the beltline region. RAPTOR-M3G(RApid Parallel Transport Of Radiation-Multiple 3D Geometries) performing full 3D transport calculation was developed by Westinghouse and KRIST(Korea Reactor Integrity Surveillance Technology) and applied for the evaluations of In-Vessel and Ex-Vessel neutron dosimetry. The reaction rates from measurement and calculation were compared and the results show good agreements each other.

Study on Conceptual Design of Pressure Vessel to Transport CNG and CO2 (CNG 및 CO2 겸용 수송을 위한 압력용기 개념 설계에 대한 연구)

  • Kim, Young-Hun
    • Journal of Ocean Engineering and Technology
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    • v.27 no.1
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    • pp.51-58
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    • 2013
  • Recently, there has been an increase in the demand for natural gas as a source of clean energy, which has increased the demand for LNG carriers. However, LNG carriers require a capital investment to obtain equipment for the regasification process, which prevents fires and explosions. Thus, on account of NIMBY, a CNG carrier is suggested that eliminates the need for regasification equipment. Meanwhile, carbon dioxide emissions are more and more regulated by international conventions such as the Kyoto Protocol. Because of this, $CO_2$ carriers have also received international attention as a methodology to transport and store $CO_2$ cargoes. Several vessels or tanks to transport and store $CO_2$ gas have been studied in various countries. This paper proposes a conceptual design for a 20ft container shaped tank to effectively transport small cargoes of $CO_2$ and CNG. The proposed pressure vessel or tank will be carried by a conventional containership or special cargo ship. The influences of the design parameters for proposed pressure vessel or tank. Including the materials, scantlings, and shape of the pressure vessel, are studied theoretically and computationally.

Neutron Flux Evaluation on the Reactor Pressure Vessel by Using Neural Network (인공신경 회로망을 이용한 압력용기 중성자 조사취화 평가)

  • Yoo, Choon-Sung;Park, Jong-Ho
    • Journal of Radiation Protection and Research
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    • v.32 no.4
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    • pp.168-177
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    • 2007
  • A neural network model to evaluate the neutron exposure on the reactor pressure vessel inner diameter was developed. By using the three dimensional synthesis method described in Regulatory Guide 1.190, a simple linear equation to calculate the neutron spectrum on the reactor pressure vessel was constructed. This model can be used in a quick estimation of fast neutron flux which is the most important parameter in the assessment of embrittlement of reactor pressure vessel. This model also used in the selection of an optimum core loading pattern without the neutron transport calculation. The maximum relative error of this model was less than 3.4% compared to the transport calculation for the calculations from cycle 1 to cycle 23 of Kori unit 1.

The Study on the Practical Problems of FOB and CIF terms under L/C transaction - with Special Emphasis on Incoterms® 2010 - (신용장 거래에 있어서 FOB, CIF조건의 적용상 문제점에 관한 연구 - Incoterms® 2010을 중심으로 -)

  • Lee, Dae-Woo;Yang, Ui-dong
    • Journal of Arbitration Studies
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    • v.21 no.3
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    • pp.189-211
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    • 2011
  • This article aims at analysing the practical problems of FOB and CIF terms relating to Incoterms$^{(R)}$2010 in case of L/C transactions and presenting the defending measures against them. According to Incoterms$^{(R)}$2010, FOB and CIF terms are to be used only for sea or inland waterway transport and require the seller deliver the goods on board the vessel nominated by the buyer at named port of shipment. So if FOB and CIF terms will be used in sea transport under L/C transaction, the seller should ship the goods on the nominated vessel and present the shipping document indicating "on board vessel" to the issuing bank but the parties agree to present the received bill of lading according to special condition on L/C which is" received bill of lading are acceptable". In practical transaction, FOB and CIF terms are usually used in aircraft cargo, container cargo or multimodal transport. these facts are a violation of Incoterms. Incoterms$^{(R)}$2010 which regulated that FOB and CIF terms may not be appropriate where goods are handed over the carrier before they are on board the vessel for example goods in container. These transactions are a temporary expedient and breach of Incoterms in the international trade which must be corrected as soon as possible.

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Safety evaluation of type B transport container for tritium storage vessel (B형 삼중수소 운반용기 안정성 평가)

  • Lee, Min-Soo;Paek, Seung-Woo;Kim, Kwang-Rag;Ahn, Do-Hee;Yim, Sung-Paal;Chung, Hong-Suk;Choi, Heui-Joo;Choi, Jeong-Won;Son, Soon-Hwan;Song, Kyu-Min
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.2
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    • pp.155-169
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    • 2007
  • A transport container for a 500 kCi tritium storage vessel was developed, which could be used for the transport of metal tritide from Wolsong TRF facility to a disposal site. The structural, thermal, shielding, and confinement analyses were performed for the container in a view of Type B. As a result of structural analysis, the developed container sustained its integrity under normal and accidental conditions. The maximum temperature increase of the inner storage vessel by radiation was evaluated at $134.8^{\circ}C at room temperature. In $800^{\circ}C$ fire test, The thermal barrier of container sustained the inner vessel at $405^{\circ}C after 30 min, which temperature was allowable for the container integrity since maximum design temperature of inner vessel was $550^{\circ}C. In the evaluation of the shielding, the activity of radiation was nearly zero on the outer surface of inner vessel. Consequently the transport container for a 500 kCi tritium was evaluated to pass all the safety tests including accidental condition, so it was concluded that the designed transport container is proper to be used.

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A study on the Optimal Economic Vessel in the South-East Asian Trade Route (동남아 항로의 최적 경제선박에 관한 연구)

  • Lee, Dong-Gon
    • 한국기계연구소 소보
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    • pp.145-155
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    • 1985
  • The recent trend in shipbuilding technology is toward development of highly economical vessels of which construction and operation costs are minimized, whereas cargo transport capacity is maximized. But, most of the vessel which are now operated by some of the nation's shipping companies are uneconomical ones built before oil crisis and consequently the companies are suffering from long-lasted deficit problem. In this paper, derivation study of optimum vessel for multi purpose cargo vessel on south-East Asian trade route is carried out to solve this problem. The Required Freight Rate is used as a measure of merits.

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H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code

  • Orsi, Roberto
    • Nuclear Engineering and Technology
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    • v.52 no.2
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    • pp.448-455
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    • 2020
  • The H.B. Robinson Unit 2 (HBR-2) pressure vessel dosimetry benchmark is an in- and ex-Reactor Pressure Vessel (RPV) neutron dosimetry benchmark based on experimental data from the HBR-2 reactor, a 2300-MW PWR designed by Westinghouse and put in operation in March 1971, openly available through the SINBAD Database at OECD/NEA data Bank. The goals of the present work were to carry out three-dimensional (3D) fixed source transport calculations in both Cartesian (X,Y,Z) and cylindrical (R,θ,Z) geometries by using the TORT-3.2 discrete ordinates code on very detailed 3D HBR-2 geometrical models and to test the latest broad-group coupled (47 neutron groups + 20 photon groups) working cross section libraries in FIDO-ANISN format with same structure as BUGLE-96, such as BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7. The results obtained with all the cited libraries were satisfactory and are here reported and compared.

Lifting off simulation of an offshore supply vessel considering ocean environmental loads and lifting off velocity

  • Jeong, Dong-Hoon;Roh, Myung-Il;Ham, Seung-Ho
    • Ocean Systems Engineering
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    • v.5 no.3
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    • pp.181-198
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    • 2015
  • An OSV (Offshore Support Vessel) is being used to install a structure which is laid on its deck or an adjacent transport barge by lifting off the structure with its own crane, lifting in the air, crossing splash zone, deeply submerging, and lastly landing it. There are some major considerations during these operations. Especially, when lifting off the structure, if operating conditions such as ocean environmental loads and lifting off velocity are not suitable, the collision can be occurred due to the relative motion between the structure and the OSV or the transport barge. To solve this problem, this study performs the physics-based simulation of the lifting off step while the OSV installs the structure. The simulation includes the calculation of dynamic responses of the OSV and the structure, including the collision detection between the transport barge and the structure. To check the applicability of the physics-based simulation, it is applied to a problem of the lifting off step by varying the ocean environmental loads and the lifting off velocity. As a result, it is confirmed that the operability of the lifting off step are affected by the conditions.

A Study on Technical Criteria of the Transport Vessel for Radioactive Wastes (방사성폐기물 수송선박의 기술기준 분석)

  • Lee, Heung-Young;Chung, Sung-Hwan;Park, Yoon-Gyu;Yoon, Suk-Joong;Nam, Jang-Soo
    • Journal of Radiation Protection and Research
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    • v.20 no.4
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    • pp.285-296
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    • 1995
  • The site of Korea Final Repository, KFR, to collect and dispose of radioactive wastes produced in nuclear power plants will be selected to seaside. As all the radwastes stored temporarily in the site of power plants should be transported by the sea, Nuclear Environmental Management Center, NEMAC, of Korea Atomic Energy Research Institute, KAERI, has been developing the sea transport system to secure safe and efficient transportation of the radwastes from the power plant sites to the final repository. Investigating the status of advanced techniques of foreign countries for transport vessels and considering inland circumstances, the technical criteria of the transport vessel have been suggested in this study. Therefore, all the radwastes will be transported safely by the sea, without releasing any radioactive material to environment even in the case of accident.

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MULTIPHASE FLOW IN EX-VESSEL COOLABILITY: DEVELOPMENT OF AN INNOVATIVE CONCEPT

  • CORRADINI MICHAEL L.
    • Nuclear Engineering and Technology
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    • v.38 no.1
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    • pp.1-10
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    • 2006
  • The interaction and mixing of high-temperature melt and water is the important technical issue in the safety assessment of water-cooled reactors to achieve ultimate core coolability. For specific advanced light water reactor (ALWR) designs, deliberate mixing of the core-melt and water is being considered as a mitigative measure, to assure ex-vessel core coolability. The paper provides the background of past experiments as well as key fundamentals that are needed for melt-water interfacial transport phenomena, thus enabling the development of innovative safety technologies for advanced LWRs that will assure ex-vessel core coolability.