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    Validation of Creep Crack Growth Life Estimation Methodology/Hot Reheat Steam Pipes 

    Source: Journal of Pressure Vessel Technology:;1994:;volume( 116 ):;issue: 003:;page 331
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper documents a validation study of a creep crack growth life estimation methodology developed by Riedel and Rice, Saxena, and Bassani which has been implemented into a Babcock & ...
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    Technical Basis for the Extension of ASME Code Case N-494 for Assessment of Austenitic Piping 

    Source: Journal of Pressure Vessel Technology:;1996:;volume( 118 ):;issue: 004:;page 513
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In 1990, the ASME Boiler and Pressure Vessel Code for Nuclear Components approved Code Case N-494 as an alternative procedure for evaluating flaws in light water reactor (LWR) ferritic piping. ...
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    Single-Edge Crack in Rectangular Sheet Subjected to End Rotations 

    Source: Journal of Applied Mechanics:;1966:;volume( 033 ):;issue: 003:;page 689
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Stress-intensity factors for single-edge cracks in rectangular sheets subjected to end rotations about the center line of the rectangle are investigated. The problem of the distribution of stress ...
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    The Effect of a Riveted Stringer on the Stress in a Sheet With a Circular Cutout 

    Source: Journal of Applied Mechanics:;1966:;volume( 033 ):;issue: 001:;page 198
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A theoretical investigation was made into the effect of a rivet-attached stringer on the stress concentrations in a thin elastic sheet with a circular cutout. The sheet and stringer are loaded ...
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    A Procedure for the Assessment of the Structural Integrity of Nuclear Pressure Vessels 

    Source: Journal of Pressure Vessel Technology:;1983:;volume( 105 ):;issue: 001:;page 28
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper presents a simple engineering procedure that the utility industry can use to assess the integrity of typical nuclear-grade pressure vessels. The procedure recognizes both brittle ...
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    Extensions of the Failure Assessment Diagram Approach Semi-Elliptical Flaw in Pressurized Cylinder 

    Source: Journal of Pressure Vessel Technology:;1985:;volume( 107 ):;issue: 001:;page 25
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A simple, viable engineering method for assessing the integrity of nuclear pressure vessels has been developed at Babcock & Wilcox. The method uses results given in a plastic fracture ...
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    Extensions of the Failure Assessment Diagram Approach Semi-Elliptical Flaw in Pressurized Cylinders—Part II 

    Source: Journal of Pressure Vessel Technology:;1986:;volume( 108 ):;issue: 004:;page 485
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Approximate closed-form J -integral expressions based on the estimation scheme for use in the Deformation Plasticity Failure Assessment Diagram (DPFAD) approach are presented for an axially oriented ...
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    An Approach to Account for Negative R-Ratio Effects in Fatigue Crack Growth Calculations for Pressure Vessels Based on Crack Closure Concepts 

    Source: Journal of Pressure Vessel Technology:;1994:;volume( 116 ):;issue: 001:;page 30
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Current fatigue crack growth procedures in the commercial nuclear industry do not clearly specify how compressive loads are to be handled and, therefore, regulatory agencies usually recommend a ...
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    Deformation Plasticity Failure Assessment Diagram (DPFAD) for Materials With Non-Ramberg-Osgood Stress-Strain Curves 

    Source: Journal of Pressure Vessel Technology:;1995:;volume( 117 ):;issue: 004:;page 346
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper presents a brief history of the evolution of the Central Electricity Generating Board’s (CEGB) R-6 failure assessment diagram (FAD) procedure used in assessing defects in structural ...
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    An Analytical Assessment of the Effects of Residual Stresses and Fracture Properties on Service Performance of Various Weld Repair Processes 

    Source: Journal of Pressure Vessel Technology:;1981:;volume( 103 ):;issue: 004:;page 373
    Author(s): J. M. Bloom
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper discusses analytical work done to assess the relative importance of residual stresses and fracture mechanics material properties on the service performance of various weld repair ...
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