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    A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers 

    Source: Journal of Pressure Vessel Technology:;2009:;volume( 131 ):;issue: 004:;page 44002
    Author(s): Weiju Ren; Robert Swindeman
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Alloys 617 and 230 are currently identified as two leading candidate metallic materials in the down selection for applications at temperatures above 760°C in the Gen IV nuclear reactor ...
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    A Review Paper on Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications 

    Source: Journal of Pressure Vessel Technology:;2009:;volume( 131 ):;issue: 002:;page 24002
    Author(s): Weiju Ren; Robert Swimdeman
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: To understand the response of Alloy 617 to long-time exposure conditions and to determine the supplementary data needs for structural components in Gen IV nuclear reactors, literature of aging ...
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    Effective Materials Property Information Management for the 21st Century 

    Source: Journal of Pressure Vessel Technology:;2011:;volume( 133 ):;issue: 004:;page 44002
    Author(s): Weiju Ren; David Cebon; Steven M. Arnold
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper discusses key principles for the development of material property information management software systems. The growing need for automated material information management is fueled, in ...
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