Volumes | Pressure Vessels and Piping Conference | American Society of Mechanical Engineers Digital Collection

Topics: Cracking (Materials) , Embrittlement , Fracture (Process) , Temperature , American Petroleum Institute , Brittle fracture , Fracture toughness , Alloy steel , Alloys , Cooling

How Potrero Utililized Flush Patches to Manage Localized Under Deposit Corrosion Damage in Waterwall Tubes

Joseph M. Mazzeo

PVP 2014; V007T07A007doi:https://doi.org/10.1115/PVP2014-28184

Abstract

View Article

PDF

Topics: Corrosion , Damage , Maintenance , Boiler tubes , Leakage , Power stations , Testing , Water

Intentional Destructive Testing: A Means for Establishing Mechanical Integrity in Plants, Facilities, and Pipelines

Chris Alexander, Brent Vyvial

PVP 2014; V007T07A008doi:https://doi.org/10.1115/PVP2014-28226

Abstract

View Article

PDF

Topics: Pipelines , Testing , Maintenance , Boundary-value problems , Inspection

Understanding Behaviors of Bolted Flanges With Non-Axisymmetric Temperature Distribution

Gong H. Jung, Minsu Kim

PVP 2014; V007T07A009doi:https://doi.org/10.1115/PVP2014-28736

Abstract

View Article

PDF

Topics: Bolted flanges , Temperature distribution , Stress , Flanges , Gaskets , Curve fitting , Finite element analysis , Heat exchangers , Leakage , Pipes

Further Developments to the Change Gasket

Stephen Bond, Ebadollah Jamalyaria

PVP 2014; V007T07A010doi:https://doi.org/10.1115/PVP2014-28948

Abstract

View Article

PDF

Topics: Gaskets , High pressure (Physics) , High temperature , Metals , Sealants

Plant Life Extension: Aging and Life Management

MAI Benchmark Campaign of International Software for Reactor Pressure Vessel Integrity Assessment

Emilie Dautreme, Emmanuel Remy, Roman Sueur, Jean-Philippe Fontes, Karine Aubert, Naoki Soneda, Masato Yamamoto, Tim Hardin, Ron Gamble

PVP 2014; V007T07A011doi:https://doi.org/10.1115/PVP2014-28212

Abstract

View Article

PDF

Topics: Computer software , Reactor vessels , Probability , Failure , Pressure vessels , Pressurized water reactors , Algorithms , Engineers , Fracture (Materials) , Fracture mechanics

License Renewal and Subsequent License Renewal in the U.S.

Garry G. Young

PVP 2014; V007T07A012doi:https://doi.org/10.1115/PVP2014-28224

Abstract

View Article

PDF

Topics: Licensing , Nuclear power stations , Nuclear industry

Extending Replacement Intervals of Elastomeric Components by Evaluating Samples Removed From Service

Jenifer T. Marchesi, William J. McBrine, Vincent Roy

PVP 2014; V007T07A013doi:https://doi.org/10.1115/PVP2014-28305

Abstract

View Article

PDF

Topics: Cables , Containment , Diaphragms (Mechanical devices) , Diaphragms (Structural) , Diesel generators , Elastomers , Electricity (Physics) , Emergencies , Engines , Gaskets

Probabilistic Pressurized Thermal Shocks Analysis for a Reactor Pressure Vessel

Guian Qian, Markus Niffenegger

PVP 2014; V007T07A014doi:https://doi.org/10.1115/PVP2014-28765

Abstract

View Article

PDF

Topics: Reactor vessels , Thermal shock , Fracture (Materials) , Failure , Probability , Transients (Dynamics) , Density , Pressure vessels , Uncertainty

Pumps and Valves

Development of Enertech’s Advanced Normally Open NozzleCheck Valves for Generation III+ Nuclear Power Plants

Haykaz Mkrtchyan

PVP 2014; V007T07A015doi:https://doi.org/10.1115/PVP2014-28082

Abstract

View Article

PDF

Topics: Nuclear power stations , Valves , Flow (Dynamics) , Computational fluid dynamics , Design , Bushings , Damage , Engineering prototypes , Gates (Closures) , Hinges

A Comparative Study of Valve Natural Frequency Estimation Using Finite Element Analysis (FEA), Raleigh’s Principles and Laboratory Tests

L. Ike Ezekoye, Preston A. Vock, Ronald S. Farrell, Richard J. Gradle

PVP 2014; V007T07A016doi:https://doi.org/10.1115/PVP2014-28095

Abstract

View Article

PDF

Topics: Finite element analysis , Valves , Testing , Design , Pipes , Resonance , Safety , Boundary-value problems , Damage , Inertia (Mechanics)

Numerical Modeling of Turbulent Cavitation Flows in Safety Relief Valves

Anthony Couzinet, Laurent Gros, Jorge Pinho, Said Chabane, Daniel Pierrat

PVP 2014; V007T07A017doi:https://doi.org/10.1115/PVP2014-28384

Abstract

View Article

PDF

Topics: Cavitation , Computer simulation , Flow (Dynamics) , Relief valves , Safety , Turbulence , Valves , Discharge coefficient , Damage , Flow visualization

Safety, Reliability and Risk Assessment

Combined Cycle Power Plant Expansion Joint Failure

Alton Reich

PVP 2014; V007T07A018doi:https://doi.org/10.1115/PVP2014-28038

Abstract

View Article

PDF

Topics: Combined cycle power stations , Expansion joints , Failure , Design , Temperature , Hot water , Engineers , Pressure

Structural Reliability Evaluation on the Pressurized Water Reactor Pressure Vessel Under Pressurized Thermal Shock Events

Hsoung-Wei Chou, Chin-Cheng Huang

PVP 2014; V007T07A019doi:https://doi.org/10.1115/PVP2014-28350

Abstract

View Article

PDF

Topics: Pressure vessels , Pressurized water reactors , Reliability , Thermal shock , Reactor vessels , Cracking (Materials) , Failure , Fracture (Process) , Nuclear power stations , Fracture mechanics

Additional Data Concerning French PWR RPV Steel to Evaluate the Relevance of a Size Effect Correction on Toughness in the Ductile-to-Brittle Transition

C. Jacquemoud, I. Delvallée-Nunio, M. Nédélec, F. Balestreri

PVP 2014; V007T07A020doi:https://doi.org/10.1115/PVP2014-28403

Abstract

View Article

PDF

Topics: Brittleness , Fracture toughness , Pressurized water reactors , Size effect , Steel , Fracture (Materials) , Databases , Geometry , Reactor vessels , Safety

Probabilistic Fracture Mechanics Analysis for Degraded Reactor Pressure Vessel in Pressurized Water Reactor Nuclear Power Plant

Kuan-Rong Huang, Chin-Cheng Huang, Hsoung-Wei Chou

PVP 2014; V007T07A021doi:https://doi.org/10.1115/PVP2014-28595

Abstract

View Article

PDF

Topics: Fracture mechanics , Nuclear power stations , Pressurized water reactors , Reactor vessels , Embrittlement , Reliability , Transients (Dynamics) , Boilers , Design , Failure

The Effect of Inspection on Maintenance Planning for Fossil Fuel Fired Power Plant

Jun Takahashi, Shinsuke Sakai

PVP 2014; V007T07A022doi:https://doi.org/10.1115/PVP2014-28599

Abstract

View Article

PDF

Topics: Fossil fuels , Inspection , Maintenance , Power stations , Probability , Failure , Uncertainty , Boiler tubes , Temperature

Toxic Substances: Storage and Transportation

Moisture Adsorption Considerations for Packaging Plutonium Oxide

James E. Laurinat, Steve J. Hensel

PVP 2014; V007T07A023doi:https://doi.org/10.1115/PVP2014-28006

Abstract

View Article

PDF

Topics: Packaging , Equilibrium (Physics) , Bearings , Containers , High temperature , Materials handling , Storage

Analysis of the Rate of Adsorption of Moisture Onto Plutonium Oxide Powders

James E. Laurinat, Matthew R. Kesterson, Steve J. Hensel

PVP 2014; V007T07A024doi:https://doi.org/10.1115/PVP2014-28073

Abstract

View Article

PDF

Topics: Containers , Containment vessels , Diffusion (Physics) , Equilibrium (Physics) , Finite element analysis , Heat conduction , Heat transfer , Hydrogen , Pressure , Radiation (Physics)

Life Extension of Hydrocarbon Equipment in Sour Environment

Abdul Wahab Al-Mithin, G. Santhosh Kumar, Mohammad Al-Shaiji, Abdul Sattar A. Hannan, Vinod Jose

PVP 2014; V007T07A025doi:https://doi.org/10.1115/PVP2014-28622

Abstract

View Article

PDF

Topics: American Petroleum Institute , Coating processes , Coatings , Cracking (Materials) , Crude oil , Damage , Diffraction , Fitness-for-service , Flight , Fracture (Process)

Design and Analysis of Shipping Container for Big Rock Decommissioned Reactor Vessel

Bruce (Bart) Slimp, Mick Papp, Phuong H. Hoang

PVP 2014; V007T07A026doi:https://doi.org/10.1115/PVP2014-28798

Abstract

View Article

PDF

Topics: Containers , Design , Reactor vessels , Rocks , Containment vessels , Steel , Structural analysis , Accidents , ASME Boiler and Pressure Vessel Code , Containment

Extending Periodic Leakage Rate Testing of 9977 Packages With Elastomeric O-Rings

Zenghu Han, Vikram N. Shah, Yung Y. Liu

PVP 2014; V007T07A027doi:https://doi.org/10.1115/PVP2014-28950

Abstract

View Article

PDF

Topics: Leakage , Seals , Testing , Temperature , Storage , Transport packages , Containment , Design , Radiation (Physics) , Radioactive substances

Design of an Experimental Apparatus to Measure the Thermal Accommodation Coefficient Between Stainless Steel Surfaces and Rarefied Helium

Rachel Green, Ernesto T. Manzo, Mustafa Hadj Nacer, Miles Greiner

PVP 2014; V007T07A028doi:https://doi.org/10.1115/PVP2014-29018

Abstract

View Article

PDF

Topics: Design , Helium , Stainless steel , Temperature , Cylinders , Engineering simulation , Simulation , Aluminum , Heat , Heat transfer

Clearance of Bulk Materials From Decommissioning Projects: Regulatory and Cost Issues

J. Devgun, D. Demoss, S. Raupp

PVP 2014; V007T07A029doi:https://doi.org/10.1115/PVP2014-29046

Abstract

View Article

PDF

Topics: Bulk solids , Clearances (Engineering) , Nuclear decommissioning , Nuclear power stations , Radioactive wastes , Demolition , Dimensions , Licensing , Materials management , Recycling

Prediction of Cladding Temperatures Within a Used Nuclear Fuel Transfer Cask Filled With Rarefied Helium

Ernesto T. Manzo, Rachel Green, Mustafa Hadj Nacer, Miles Greiner

PVP 2014; V007T07A030doi:https://doi.org/10.1115/PVP2014-29048

Abstract

View Article

PDF

Topics: Cladding systems (Building) , Helium , Nuclear fuels , Temperature , Fuels , Heat , Engineering simulation , Simulation , Collisions (Physics) , Cylinders