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    Special Issue: Seventh International Symposium on Supercritical Water Cooled Reactors 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001:;page 10301
    Author(s): Schulenberg, Thomas
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This special issue of the Journal of Nuclear Engineering and Radiation Science features selected papers from the 7th International Symposium on Supercritical WaterCooled Reactors (ISSCWR7), held from March 15 to 18, 2015, ...
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    Special Issue: Selected Papers from the 8th International Symposium on Supercritical Water-Cooled Reactors 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001:;page 10301
    Author(s): Schulenberg, Thomas
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: pecial issue of the ASME Journal of Nuclear Engineering and Radiation Science comprises selected papers from the eighth International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-8), held from Mar. 13 to 15, ...
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    Concept of a Small Modular SCWR With Horizontal Fuel Assemblies 

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003:;page 34501-1
    Author(s): Schulenberg, Thomas; Otic, Ivan
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Based on the concept of the high performance light water reactor (HPLWR), an innovative concept of a small modular reactor is presented, which shall have smaller peak cladding temperatures than the HPLWR due to better ...
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    Numerical Simulation of a Steam Injector for Passive Residual Heat Removal 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 003:;page 031105-1
    Author(s): Schulenberg, Thomas; Heinze, David
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In the case of depressurization of a supercritical water-cooled reactor (SCWR), the steam pressure can be used to pump coolant back into the reactor, either by using a turbine driven pump or a steam injector. The latter ...
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    Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001:;page 11005
    Author(s): Schulenberg, Thomas; Li, Hongbo
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: While supercritical water is a perfect coolant with excellent heat transfer, a temporary decrease of the system pressure to subcritical conditions, either during intended transients or by accident, can easily cause a boiling ...
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    Special Section: Selected Papers From the Ninth International Symposium on Supercritical Water-Cooled Reactors 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 003:;page 030301-1
    Author(s): Leung, Laurence; Guzonas, David; Schulenberg, Thomas
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The Ninth International Symposium on Supercritical Water-Cooled Reactors (IS-SCWRs) was successfully held on Mar. 11–13, 2019 at the Vancouver Marriott Hotel, Vancouver, BC, Canada. It was hosted by the Canadian Nuclear ...
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    A Physically Based, One Dimensional Two Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 002:;page 21002
    Author(s): Heinze, David; Schulenberg, Thomas; Behnke, Lars
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A simulation model for the direct contact condensation of steam in subcooled water is presented that allows determination of major parameters of the process, such as the jet penetration length. Entrainment of water by the ...
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    Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001:;page 11005
    Author(s): Raquأ©, Manuel; Schulenberg, Thomas; Zeiger, Tobias
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The supercritical water reactor (SCWR) fuel qualification test is an inpile test of a fourrod fuel assembly at supercritical pressure inside a research reactor, which is operated at atmospheric pressure. The risk of ...
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    Numerical Study of Fluid–Structure Interaction With Heat Transfer at Supercritical Pressure in a Fuel Rod Assembly 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001:;page 11013
    Author(s): Hartig, Maximilian; Schulenberg, Thomas; Batta, Abdalla
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Irregular temperature profiles inside nuclear reactors cause the deformation of fuel rods. Due to difficulties in implementing this phenomenon, it is usually neglected in computational fluid dynamics (CFD) analyses. ...
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    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(s): Vojacek, Ales; Ruzickova, Mariana; Schulenberg, Thomas
    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). ...
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