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    Assessment of Weld Heat-Affected Zones in a Reactor Vessel Material 

    Source: Journal of Engineering Materials and Technology:;1978:;volume( 100 ):;issue: 003:;page 267
    Author(s): T. U. Marston; W. Server
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The mechanical properties of weld heat-affected zones (HAZ’s) associated with the heavy section, nuclear quality weldments are evaluated and found to be superior to those of the parent base ...
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    A Description of a Study for the Thermal Anneal of Neutron-Embrittled Reactor Vessel Materials 

    Source: Journal of Engineering Materials and Technology:;1978:;volume( 100 ):;issue: 003:;page 272
    Author(s): T. R. Mager; T. U. Marston
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A number of early light water reactor plants were constructed from materials having low initial Charpy upper shelf values and high copper and phosphorus content. As these elements have been ...
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