YaBeSH Engineering and Technology Library

    • Journals
    • PaperQuest
    • YSE Standards
    • YaBeSH
    • Login
    View Item 
    •   YE&T Library
    • ASME
    • Journal of Nuclear Engineering and Radiation Science
    • View Item
    •   YE&T Library
    • ASME
    • Journal of Nuclear Engineering and Radiation Science
    • View Item
    • All Fields
    • Source Title
    • Year
    • Publisher
    • Title
    • Subject
    • Author
    • DOI
    • ISBN
    Advanced Search
    JavaScript is disabled for your browser. Some features of this site may not work without it.

    Archive

    Design of an In Pile SCWR Fuel Qualification Test Loop

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001::page 11003
    Author:
    Vojacek, Ales
    ,
    Ruzickova, Mariana
    ,
    Schulenberg, Thomas
    DOI: 10.1115/1.4030872
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In the development of the supercritical watercooled reactor (SCWR), an inpile fuel assembly test loop has been designed within the framework of the joint Chinese–European project, called SCWRFQT (Fuel Qualification Test). This paper presents the basic design of the loop with its auxiliary and safety systems, which has been examined in detail by thermalhydraulic analyses in order to achieve operation of the loop above the thermodynamic critical point of water (374آ°C, 22.1آ MPa) and checked by stress analyses to assure safe operation. The designed experimental loop for fuel qualification in supercritical water consists of a closed pressurized water circuit with forced circulation of the coolant through the test section—the active channel which is intended to be installed into the existing research pooltype reactor LVR15. The active channel will be operated at temperatures and pressures which are typical for the highperformance light water reactor (HPLWR). A thickwalled pressure tube made from austenitic stainless steel, which is able to withstand the high system pressure, encloses the active channel. It contains four fuel rods with UO2 (enrichment of 19.7% U235) with a total heating power of ∼64  kW and a recuperator in order to achieve hot channel conditions as they are expected to occur in the evaporator of the HPLWR. The internal flow is realized so as to prevent the creep condition of the pressure tube. An internal Utube cooler serves as heat sink and is connected to the secondary circuit. The entire active channel is isolated from water of the reactor pool by an air gap between the pressure tube and an aluminum displacer. The test section with fuel is connected to a 300آ°C closed loop and to a primary pump located outside the reactor building as well as safety systems and auxiliary systems, such as purification and measurement circuits, which are all connected with the primary circuit.
    • Download: (1.008Mb)
    • Show Full MetaData Hide Full MetaData
    • Get RIS
    • Item Order
    • Go To Publisher
    • Price: 5000 Rial
    • Statistics

      Design of an In Pile SCWR Fuel Qualification Test Loop

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/162169
    Collections
    • Journal of Nuclear Engineering and Radiation Science

    Show full item record

    contributor authorVojacek, Ales
    contributor authorRuzickova, Mariana
    contributor authorSchulenberg, Thomas
    date accessioned2017-05-09T01:32:07Z
    date available2017-05-09T01:32:07Z
    date issued2016
    identifier issn2332-8983
    identifier otherNERS_2_1_011003.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/162169
    description abstractIn the development of the supercritical watercooled reactor (SCWR), an inpile fuel assembly test loop has been designed within the framework of the joint Chinese–European project, called SCWRFQT (Fuel Qualification Test). This paper presents the basic design of the loop with its auxiliary and safety systems, which has been examined in detail by thermalhydraulic analyses in order to achieve operation of the loop above the thermodynamic critical point of water (374آ°C, 22.1آ MPa) and checked by stress analyses to assure safe operation. The designed experimental loop for fuel qualification in supercritical water consists of a closed pressurized water circuit with forced circulation of the coolant through the test section—the active channel which is intended to be installed into the existing research pooltype reactor LVR15. The active channel will be operated at temperatures and pressures which are typical for the highperformance light water reactor (HPLWR). A thickwalled pressure tube made from austenitic stainless steel, which is able to withstand the high system pressure, encloses the active channel. It contains four fuel rods with UO2 (enrichment of 19.7% U235) with a total heating power of ∼64  kW and a recuperator in order to achieve hot channel conditions as they are expected to occur in the evaporator of the HPLWR. The internal flow is realized so as to prevent the creep condition of the pressure tube. An internal Utube cooler serves as heat sink and is connected to the secondary circuit. The entire active channel is isolated from water of the reactor pool by an air gap between the pressure tube and an aluminum displacer. The test section with fuel is connected to a 300آ°C closed loop and to a primary pump located outside the reactor building as well as safety systems and auxiliary systems, such as purification and measurement circuits, which are all connected with the primary circuit.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleDesign of an In Pile SCWR Fuel Qualification Test Loop
    typeJournal Paper
    journal volume2
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4030872
    journal fristpage11003
    journal lastpage11003
    treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001
    contenttypeFulltext
    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian
     
    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian