Proceedings of the ASME Pressure Vessels & Piping Conference - 2020 presented at ASME 2020 Pressure Vessels & Piping Conference, August 3, online Volume 1 Codes and standards

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Körperschaften: ASME Pressure Vessels & Piping Conference (VerfasserIn), American Society of Mechanical Engineers (Herausgebendes Organ), American Society of Mechanical Engineers Pressure Vessels and Piping Division (SponsorIn)
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Sprache:eng
Veröffentlicht: New York, NY the American Society of Mechanical Engineers 2020
Red Hook, NY Curran Associates, Inc.
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Titel Jahr Verfasser
PVP2020-21043 Fatigue Benchmark Comparison Effort Between Code Aster and CNNC/NPIC Software: Part 2 2020 Xie, Hai
PVP2020-21262 Further Evidence of Margin for Environmental Effects, Termed Fen-Threshold, in the ASME Section lll Design Fatigue Curve for Austenitic Stainless Steels Through the Interaction Between the PWR Environment and Surface Finish 2020 McLennan, Alec
PVP2020-21422 INCEFA-PLUS Project: The Impact of Using Fatigue Data Generated From Multiple Specimen Geometries on the Outcome of a Regression Analysis 2020 Mclennan, Alec
PVP2020-21585 Further Development of Fatigue Crack Growth Expressions for Austenitic Stainless Steels in PWR Water and Additional Validation of the WTKR Method 2020 Mann, Jonathan
PVP2020-21678 Environmental Fatigue Screening for Subsequent License Renewal 2020 Walker, Adam P.
PVP2020-21828 Recent Argonne National Laboratory Estimated Thermal Expansion Coefficients for Reactor Pressure Boundary Base Metal, Similar and Dissimilar Metal Welds 2020 Mohanty, Subhasish
PVP2020-21632 Investigation Into Methods for Determining Moment Ranges at Piping Tees and Branches 2020 Pellereau, Ben
PVP2020-21841 Fatigue Consideration of Layered Vessels 2020 Xu, Kang
PVP2020-21790 Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK 2020 Underwood, Nicholas
PVP2020-21612 Codes and Standards for Managing Degradation of Boilers in Service 2020 Site, Corrado Delle
PVP2020-21441 Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel 2020 Shimodaira, Masaki
PVP2020-21452 Assessment of Flaw Interaction Under Combined Tensile and Bending Stresses: Suitability of ASME Code Case N877-1 2020 Dulieu, Pierre
PVP2020-21549 Stress Intensity Factor and Crack Opening Area of Circumferentially-Cracked Pipe Under Torsion Moment 2020 Huang, Yifan
PVP2020-21806 Prediction of Collapse Load Reduction due to Non-Aligned Multiple Flaws 2020 lwamatsu, Fuminori
PVP2020-21672 Allowable External Flaws and Acceptance Standards for High Toughness Ductile Pipes Subjected to Bending Moment and Internal Pressure 2020 Hasegawa, Kunio
PVP2020-21513 Effect of Neutron Irradiation on the Mechanical Properties of an A508 CI.2 Forging Irradiated in a BAMI Capsule 2020 Uytdenhouwen, Inge
PVP2020-21421 Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor 2020 Lu, Kai
PVP2020-21493 Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components 2020 Barua, B.
PVP2020-21058 Application of Ultrasonic Guided Wave in LMPH Tube of Ethylene Cracking Furnace 2020 Ding, Ju
PVP2020-21352 Research on Chinese Codes and Standards of Heat Transfer Performance Testing for Heat Exchangers 2020 Ren, Bin
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