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

Volume 7: Operations, Applications, and Components

Operations, Applications, and Components

Aging Management and Life Extension

Reactor Pressure Vessel: EDF R&D Program to Support Lifetime Management

Jean-Philippe Fontes, Christelle Raynaud, Alain Martin, Aurore Parrot, Anna Dahl, Dominique Moinereau, Patrick Todeschini, Henriette Churier-Bossenec, Claude Pages

PVP 2011; 3-13https://doi.org/10.1115/PVP2011-57088

Abstract

View Articletitled, Reactor Pressure Vessel: EDF R&D Program to Support Lifetime Management

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Topics: Reactor vessels , Embrittlement , Nuclear power stations , Steel , Brittleness , Computer simulation , Concretes , Containment , Design , Fracture (Materials)

Operating Nuclear Plant License Renewal Program Status and Trends

Garry G. Young

PVP 2011; 15-18https://doi.org/10.1115/PVP2011-57127

Abstract

View Articletitled, Operating Nuclear Plant License Renewal Program Status and Trends

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Topics: Licensing , Nuclear power stations , Stability , Nuclear power plant operations , Safety

Challenges Associated With License Renewal Fatigue Evaluations for an Older-Vintage BWR Plant: Part 2

Raymond M. Pace, Fred J. Mogolesko, Terry J. Herrmann, George Mileris, Harry L. Gustin, Tyler Novotny

PVP 2011; 19-27https://doi.org/10.1115/PVP2011-57128

Abstract

View Articletitled, Challenges Associated With License Renewal Fatigue Evaluations for an Older-Vintage BWR Plant: Part 2

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Topics: Boiling water reactors , Fatigue , Licensing , Fatigue analysis , Nuclear power stations , Design , Electric arc furnaces , Nozzles , Nuclear reactor coolants , Pipes

Analysis of Cured-in-Place Piping for a Nuclear Plant Application

Alton Reich, Victor Newman, Roberto Di Salvo, John Charest

PVP 2011; 29-34https://doi.org/10.1115/PVP2011-57265

Abstract

View Articletitled, Analysis of Cured-in-Place Piping for a Nuclear Plant Application

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Topics: Nuclear power stations , Pipes , Maintenance , Design , ASTM International , Leakage , Pressure , Pressure pipes , Sewer systems , Water

Continuous Creep Damage Monitoring Using a Novel Potential Drop Technique

Catrin M. Davies, Peter Nagy, Aditya Narayanan, Peter Cawley

PVP 2011; 35-39https://doi.org/10.1115/PVP2011-57325

Abstract

View Articletitled, Continuous Creep Damage Monitoring Using a Novel Potential Drop Technique

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Topics: Creep , Damage , Alternating current potential drop techniques , Anisotropy , Cavities , Cracking (Materials) , Electrical resistivity , Electrodes , Fracture (Process) , Grain boundaries

The Influence of Chemistry Concentration Uncertainty on the Probabilistic Fracture Mechanics Analysis

Bo-Yi Chen, Chin-Cheng Huang, Hsuing-Wei Chou, Ru-Feng Liu, Hsien-Chou Lin

PVP 2011; 41-47https://doi.org/10.1115/PVP2011-57470

Abstract

View Articletitled, The Influence of Chemistry Concentration Uncertainty on the Probabilistic Fracture Mechanics Analysis

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Topics: Chemistry , Fracture mechanics , Uncertainty , Fracture (Materials) , Fracture (Process) , Probability , Reactor vessels , Welded joints , Boiling water reactors , Ductility

Pre Test Calculations on TOPFLOW PTS Experiment With NEPTUNE_CFD Code

A. Martin, C. Raynaud, P. Pe´turaud, C. Heib, F. Dubois, F. Huvelin, A. Barbier

PVP 2011; 49-56https://doi.org/10.1115/PVP2011-57784

Abstract

View Articletitled, Pre Test Calculations on TOPFLOW PTS Experiment With NEPTUNE_CFD Code

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Topics: Accidents , Coolants , Cooling , Databases , Emergencies , Engineering simulation , Reactor vessels , Simulation , Thermal shock , Transients (Dynamics)

How a Knowledge Data Base Assists the Process of Aging Management

Horst Rothenho¨fer, Friedrich Scho¨ckle, Gu¨nter Ko¨nig

PVP 2011; 57-63https://doi.org/10.1115/PVP2011-57895

Abstract

View Articletitled, How a Knowledge Data Base Assists the Process of Aging Management

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Topics: Databases , Nuclear power stations , Surveillance , Cycles , Dimensions , Maintenance , Safety , Teams

Fatigue Cycle Monitoring

Kirby Woods, Kenneth Thomas

PVP 2011; 65-71https://doi.org/10.1115/PVP2011-58036

Abstract

View Articletitled, Fatigue Cycle Monitoring

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Topics: Cycles , Fatigue , Transients (Dynamics) , Stress , Design , Analytical design , Deflection , Fatigue analysis , Licensing , Life extension

Fatigue and SCC Lifetime Enhancement of Steels by Means of Laser Peening

Lloyd A. Hackel, C. Brent Dane, Jon Rankin, Fritz Harris, Chanh Truong, Serena Marley

PVP 2011; 73-84https://doi.org/10.1115/PVP2011-58037

Abstract

View Articletitled, Fatigue and SCC Lifetime Enhancement of Steels by Means of Laser Peening

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Topics: Fatigue , Laser hardening , Steel , Stress , Stress corrosion cracking

EDF Ageing Management: Status and Ongoing Developments

Claude Faidy

PVP 2011; 85-91https://doi.org/10.1115/PVP2011-58058

Abstract

View Articletitled, EDF Ageing Management: Status and Ongoing Developments

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Topics: Cables , Civil engineering , Instrumentation , Knowledge management , Safety , Turbines

Statement of the French Safety Authority Concerning the Behaviour of 900 MWe PWR RPV Between 30 and 40 Years in Operation

L. Monin

PVP 2011; 93-99https://doi.org/10.1115/PVP2011-58077

Abstract

View Articletitled, Statement of the French Safety Authority Concerning the Behaviour of 900 MWe PWR RPV Between 30 and 40 Years in Operation

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Topics: Pressurized water reactors , Safety , Maintainability , Radiation (Physics) , Reactor vessels , Regulations

Monitoring, Diagnostics and Inspection

Non Destructive Inspection of Nickel Base Alloys in France

F. Champigny, D. Deforge, E. Lemaire

PVP 2011; 103-107https://doi.org/10.1115/PVP2011-57021

Abstract

View Articletitled, Non Destructive Inspection of Nickel Base Alloys in France

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Topics: Alloys , Nickel , Nondestructive evaluation , Welded joints , Water , Carbon steel , Clevises , Crack propagation , Hazards , In-service inspection

On Identification of Leaky Pipeline Parameters via Monte Carlo Simulation

Kamal A. F. Moustafa, Samir A. Emam, Yousef S. Haik

PVP 2011; 109-112https://doi.org/10.1115/PVP2011-57036

Abstract

View Articletitled, On Identification of Leaky Pipeline Parameters via Monte Carlo Simulation

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Topics: Leakage , Pipelines , Simulation , Friction , Computer simulation , Flow (Dynamics) , Noise (Sound) , Pressure , Simulation results

Overview of Regulations and Codes/Standards for Inspection Intervals of Above Ground Storage Tanks

Takayasu Tahara, Shinsuke Sando

PVP 2011; 113-123https://doi.org/10.1115/PVP2011-57105

Abstract

View Articletitled, Overview of Regulations and Codes/Standards for Inspection Intervals of Above Ground Storage Tanks

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Topics: Inspection , Regulations , Storage tanks , American Petroleum Institute , Fire

In-Service Inspection Ultrasonic Testing of Reactor Pressure Vessel Welds for Assessing Flaw Density and Size Distribution Per 10 CFR 50.61a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock

Edmund J. Sullivan, Michael T. Anderson, Wallace Norris

PVP 2011; 125-130https://doi.org/10.1115/PVP2011-58045

Abstract

View Articletitled, In-Service Inspection Ultrasonic Testing of Reactor Pressure Vessel Welds for Assessing Flaw Density and Size Distribution Per 10 CFR 50.61a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock

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Topics: Density , Fracture toughness , In-service inspection , Reactor vessels , Thermal shock , Ultrasonic testing , Welded joints , ASME Standards , Cracking (Materials) , Fracture (Process)

Operations and Maintenance of Pressure Vessels, Heat Exchangers, and Structures

The Combination of Modern Sealing Materials to Assist in the Reduction of Flange Deterioration

Russ Currie

PVP 2011; 133-138https://doi.org/10.1115/PVP2011-57010

Abstract

View Articletitled, The Combination of Modern Sealing Materials to Assist in the Reduction of Flange Deterioration

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Topics: Flanges , Sealants , Sealing (Process) , Composite materials , Corrosion , Gaskets

The Vital Role of the Corrosion/Materials Engineer in the Life Cycle Management of Pressure Equipment

John Reynolds

PVP 2011; 139-146https://doi.org/10.1115/PVP2011-57012

Abstract

View Articletitled, The Vital Role of the Corrosion/Materials Engineer in the Life Cycle Management of Pressure Equipment

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Topics: Corrosion , Engineers , Life cycle management , Pressure equipment , Materials degradation , Chemistry , Containment , Corrosion protection , Failure , Maintenance

Guidelines for Repair Welding of Pressure Equipment in Refinery and Chemical Plants: Part 3—Repair Welding for Specific Materials - Carbon Steel, High Tensile Steel and Cr-Mo Steel

Rinzo Kayano, Masamitsu Abe, Yukio Hirai

PVP 2011; 147-155https://doi.org/10.1115/PVP2011-57079

Abstract

View Articletitled, Guidelines for Repair Welding of Pressure Equipment in Refinery and Chemical Plants: Part 3—Repair Welding for Specific Materials - Carbon Steel, High Tensile Steel and Cr-Mo Steel

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Topics: Carbon steel , High strength steel , Maintenance , Pressure equipment , Steel , Welding , Cracking (Materials) , Fracture (Process) , Heat exchangers , Heat treating (Metalworking)

Inadvertent Blowdown Event in a Nuclear Boiling Water Reactor

Robert Engel

PVP 2011; 157-164https://doi.org/10.1115/PVP2011-57095

Abstract

View Articletitled, Inadvertent Blowdown Event in a Nuclear Boiling Water Reactor

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Topics: ASME Standards , Boiling water reactors , Circuits , Cycles , Deformation , Emergencies , Fatigue , Fracture (Materials) , Fracture (Process) , Inspection

Guidelines for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 4—Weld Repair for Specific Materials - Stainless Steel, Clad Steel and Dissimilar Joints

Tsukasa Okazaki, Rinzo Kayano, Takahisa Hoshika, Shinta Niimoto

PVP 2011; 165-171https://doi.org/10.1115/PVP2011-57142

Abstract

View Articletitled, Guidelines for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 4—Weld Repair for Specific Materials - Stainless Steel, Clad Steel and Dissimilar Joints

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Topics: Maintenance , Pressure equipment , Stainless steel , Steel , Welding , Overlays (Materials engineering)

Guidelines for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 6—Material Degradation and Repair Welding

Tomoaki Kiso, Rinzo Kayano, Eiki Nagashima, Yasuhiro Hara

PVP 2011; 173-178https://doi.org/10.1115/PVP2011-57281

Abstract

View Articletitled, Guidelines for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 6—Material Degradation and Repair Welding

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Topics: Maintenance , Materials degradation , Pressure equipment , Welding , Damage

Guidelines for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 2—Repair Welding Method

Keisuke Shiga, Yukio Hirai, Ogayu Yasushi

PVP 2011; 179-185https://doi.org/10.1115/PVP2011-57289

Abstract

View Articletitled, Guidelines for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 2—Repair Welding Method

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Topics: Maintenance , Pressure equipment , Welding , Plates (structures) , Welding research

A Remaining Life Assessment for Shell-to-Skirt Juncture of Coke Drum With Crack-Like Flaws

Masaaki Oka, Himsar Ambarita, Masashi Daimaruya, Hiroyuki Fujiki, Hidetoshi Kobayashi

PVP 2011; 187-192https://doi.org/10.1115/PVP2011-57305

Abstract

View Articletitled, A Remaining Life Assessment for Shell-to-Skirt Juncture of Coke Drum With Crack-Like Flaws

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Topics: Coke , Fracture (Materials) , Remaining life assessment , Shells , Cycles , Temperature , Boundary-value problems , Cooling , Failure , Fatigue

Management of PWR Steam Generator Tube Plugging and Primary Flow-Rate Predictions

Olivier Brunin

PVP 2011; 193-200https://doi.org/10.1115/PVP2011-57357

Abstract

View Articletitled, Management of PWR Steam Generator Tube Plugging and Primary Flow-Rate Predictions

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Topics: Boilers , Flow (Dynamics) , Pressurized water reactors , Nondestructive evaluation , Clearances (Engineering) , Heat , Maintenance , Nuclear fuels , Nuclear reactor coolants , Safety

Guideline for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 5—Repair Welding for Specific Materials - Heat Resistance Alloy and Non-Ferrous Metals

Hirohisa Watanabe, Keisuke Shiga, Atsushi Ohno

PVP 2011; 201-206https://doi.org/10.1115/PVP2011-57788

Abstract

View Articletitled, Guideline for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 5—Repair Welding for Specific Materials - Heat Resistance Alloy and Non-Ferrous Metals

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Topics: Alloys , Heat , Maintenance , Nonferrous metals , Pressure equipment , Welding , Chemical industry , Copper , Nickel , Petroleum

Simultaneous Measurement of Velocity and Temperature Downstream of a Heated Cylinder

Pe´ter Bencs, Szila´rd Szabo´, Ro´bert Borda´s, Katharina Za¨hringer, Dominique The´venin

PVP 2011; 207-212https://doi.org/10.1115/PVP2011-57789

Abstract

View Articletitled, Simultaneous Measurement of Velocity and Temperature Downstream of a Heated Cylinder

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Topics: Cylinders , Temperature , Vortices , Flow (Dynamics) , Vortex street , Computer simulation , Electric power transmission , Forced convection , Heat exchangers , Heat losses

Guidelines for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 1—General

Eiichi Yamamoto, Takayasu Tahara, Yukinobu Matsushita, Fumiyoshi Minami

PVP 2011; 213-218https://doi.org/10.1115/PVP2011-57809

Abstract

View Articletitled, Guidelines for Repair Welding of Pressure Equipment in Refineries and Chemical Plants: Part 1—General

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Topics: Maintenance , Pressure equipment , Welding , Chemical industry , Materials degradation , Petrochemicals , Petroleum , Pressure vessels , Process industries

Life-Cycle Management of Pressurized Fixed Equipment

David A. Osage, David R. Thornton, Philip A. Henry

PVP 2011; 219-233https://doi.org/10.1115/PVP2011-57903

Abstract

View Articletitled, Life-Cycle Management of Pressurized Fixed Equipment

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Topics: Life cycle management , Damage , Design , Engineering standards , American Petroleum Institute , Construction , Fitness-for-service , In-service inspection , Inspection , Maintenance

Pumps and Valves

Advances in the Design and Qualification of Main Steam and Main Feedwater Isolation Valves (MSIV and MFIV) With Type A, Gas Hydraulic Actuators

Richard J. Gradle, Floyd A. Bensinger

PVP 2011; 237-243https://doi.org/10.1115/PVP2011-57124

Abstract

View Articletitled, Advances in the Design and Qualification of Main Steam and Main Feedwater Isolation Valves (MSIV and MFIV) With Type A, Gas Hydraulic Actuators

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Topics: Design , Feedwater , Hydraulic actuators , Steam , Valves

Type Acceptance Testing of Valves: Petroleum Industry User Experience

Tony Smart, Ayman Cheta

PVP 2011; 245-250https://doi.org/10.1115/PVP2011-57137

Abstract

View Articletitled, Type Acceptance Testing of Valves: Petroleum Industry User Experience

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Topics: Petroleum industry , Testing , Valves , Engineering standards , Pressure , Reliability , Temperature

Development of an ASME QME-1-2007 Program for Safety Related Active Valve Assemblies for Advanced Plants

L. Ike Ezekoye, Edward W. Drake

PVP 2011; 251-254https://doi.org/10.1115/PVP2011-57722

Abstract

View Articletitled, Development of an ASME QME-1-2007 Program for Safety Related Active Valve Assemblies for Advanced Plants

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Topics: Safety , Valves , Nuclear power stations , Manufacturing , Equipment qualification , Valve actuators

Qualification and Testing

Underwater Testing of a Typical Ambient-Cure Epoxy Resin for Composite Repairs of Structural Piping and Vessels

Timothy S. Mally, Allison L. Johnston, Michael W. Keller, Roger H. Walker

PVP 2011; 257-263https://doi.org/10.1115/PVP2011-57643

Abstract

View Articletitled, Underwater Testing of a Typical Ambient-Cure Epoxy Resin for Composite Repairs of Structural Piping and Vessels

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Topics: Composite materials , Epoxy resins , Maintenance , Pipes , Polymer composites , Testing , Vessels , Resins , Carbon fibers , Hardening (Curing)

Hydraulic Qualification and Testing of Nuclear Equipments and Installations: Technical Considerations by Application of European Harmonized Standard and Different Codes; KTA, ASME, RCC-M, Etc.

Georges Bezdikian

PVP 2011; 265-276https://doi.org/10.1115/PVP2011-58057

Abstract

View Articletitled, Hydraulic Qualification and Testing of Nuclear Equipments and Installations: Technical Considerations by Application of European Harmonized Standard and Different Codes; KTA, ASME, RCC-M, Etc.

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Topics: Testing , Construction , Nuclear power stations , ASME Standards , Engineering standards

Safety, Reliability and Risk Assessment

Life Prediction of T91 Welded Joint and its Engineering Application Under Consideration of Welding Residual Stresses

Changyu Zhou, Guodong Zhang

PVP 2011; 279-283https://doi.org/10.1115/PVP2011-57076

Abstract

View Articletitled, Life Prediction of T91 Welded Joint and its Engineering Application Under Consideration of Welding Residual Stresses

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Topics: Residual stresses , Welded joints , Welding , Damage , Creep , Stress , American Petroleum Institute , Computer simulation , Constitutive equations , High temperature

Assessment of Safety Integrity of LDPE Tubular Reactor With Emergency Pressure Relief Requirement Consideration

Jianxin Zhu, Xuedong Chen, Zhibin Ai, Weihe Guan, Lijian Zhuang, Xiangrong Fang

PVP 2011; 285-290https://doi.org/10.1115/PVP2011-57553

Abstract

View Articletitled, Assessment of Safety Integrity of LDPE Tubular Reactor With Emergency Pressure Relief Requirement Consideration

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Topics: Emergencies , Pressure , Reliability , Safety

Mechanical Collateral Damage Assessment of Reactor Vessel Bottom Mounted Nozzles: Part I—Requirements and Methodology

Tama´s R. Liszkai

PVP 2011; 291-300https://doi.org/10.1115/PVP2011-57804

Abstract

View Articletitled, Mechanical Collateral Damage Assessment of Reactor Vessel Bottom Mounted Nozzles: Part I—Requirements and Methodology

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Topics: Damage assessment , Nozzles , Reactor vessels , Pipes , Alloys , Stress , Failure , Pressurized water reactors , Safety , Design

Mechanical Collateral Damage Assessment of Reactor Vessel Bottom Mounted Nozzles: Part II—Analysis and Applications

Tama´s R. Liszkai

PVP 2011; 301-309https://doi.org/10.1115/PVP2011-57805

Abstract

View Articletitled, Mechanical Collateral Damage Assessment of Reactor Vessel Bottom Mounted Nozzles: Part II—Analysis and Applications

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Topics: Damage assessment , Nozzles , Reactor vessels , Pipes , Alloys , Stress , Failure , Pressurized water reactors , Safety , Design

Irradiation Performance Update on Advanced Nuclear Fuel of PLUS7™

Young Ki Jang, Kyeong Lak Jeon, Jae Ik Kim, Jung Cheol Shin, Yong Hwan Kim, Sun Tack Hwang, Man Soo Kim, Tae Hyoung Lee, Yong Bae Yoon, Tae Wan Kim

PVP 2011; 311-315https://doi.org/10.1115/PVP2011-57927

Abstract

View Articletitled, Irradiation Performance Update on Advanced Nuclear Fuel of PLUS7™

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Topics: Irradiation (Radiation exposure) , Nuclear fuels , Fuels , Cycles , Manufacturing , Deformation , Surveillance , Corrosion , Creep , Economics

Student Papers

Very High Cycle Fatigue Behavior and Life Prediction of a Low Strength Weld Metal at Moderate Temperature

Ming-Liang Zhu, Fu-Zhen Xuan, Zhengdong Wang

PVP 2011; 317-329https://doi.org/10.1115/PVP2011-57473

Abstract

View Articletitled, Very High Cycle Fatigue Behavior and Life Prediction of a Low Strength Weld Metal at Moderate Temperature

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Topics: High cycle fatigue , Metals , Temperature , Cycles , Fracture (Materials) , Failure , Welding , Fatigue failure , Fatigue life , Fatigue properties

Recent Developments in ARCMAC and Related Creep Strain Monitoring Techniques

Aditya Narayanan, Andy Morris, Catrin Mair Davies, John Dear

PVP 2011; 331-336https://doi.org/10.1115/PVP2011-57948

Abstract

View Articletitled, Recent Developments in ARCMAC and Related Creep Strain Monitoring Techniques

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Topics: Creep , High temperature , Strain measurement , Gages , Pipes , Steam , Image formation , Power stations , Resolution (Optics) , Silicon nitride ceramics

Size Effects on Fracture in Uncontained Plasticity Conditions in 304(L) Stainless Steel

Andrew P. Wasylyk, Andrew H. Sherry

PVP 2011; 337-344https://doi.org/10.1115/PVP2011-57950

Abstract

View Articletitled, Size Effects on Fracture in Uncontained Plasticity Conditions in 304(L) Stainless Steel

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Topics: Fracture (Materials) , Plasticity , Stainless steel , Fracture toughness , Collapse , Ductile fracture , Failure mechanisms , Size effect , Tension

Toxic Substances: Storage and Transportation

Thermal Analysis of a 9975 Package in a Facility Fire Accident

Narendra K. Gupta

PVP 2011; 347-353https://doi.org/10.1115/PVP2011-57005

Abstract

View Articletitled, Thermal Analysis of a 9975 Package in a Facility Fire Accident

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Topics: Accidents , Fire , Thermal analysis , Transport packages , Design , Containers , Storage , Bearings , Regulations , Rivers

Hydrogen Concentrations During Storage of 3013 Oxide Samples

N. M. Askew, J. E. Laurinat, S. J. Hensel

PVP 2011; 355-359https://doi.org/10.1115/PVP2011-57006

Abstract

View Articletitled, Hydrogen Concentrations During Storage of 3013 Oxide Samples

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Topics: Hydrogen , Storage

Radioactive Material Packaging Torque Requirements Compliance

Robert W. Watkins, Daniel R. Leduc, Allen C. Smith

PVP 2011; 361-364https://doi.org/10.1115/PVP2011-57203

Abstract

View Articletitled, Radioactive Material Packaging Torque Requirements Compliance

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Topics: Packaging , Radioactive substances , Torque , Containers , Containment , Fasteners , Testing

Issues Associated With Safe Packaging and Transport of Nanoparticles

Allen C. Smith, Narendra Gupta

PVP 2011; 365-368https://doi.org/10.1115/PVP2011-57662

Abstract

View Articletitled, Issues Associated With Safe Packaging and Transport of Nanoparticles

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Topics: Nanoparticles , Packaging , Hazardous substances , Transportation systems

Containment Vessel Temperature for Pu-238 Heat Source Container Under Ambient, Free Convection and Low Emissivity Cooling Conditions

Allen C. Smith, Narendra Gupta

PVP 2011; 369-375https://doi.org/10.1115/PVP2011-57664

Abstract

View Articletitled, Containment Vessel Temperature for Pu-238 Heat Source Container Under Ambient, Free Convection and Low Emissivity Cooling Conditions

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Topics: Containers , Containment vessels , Cooling , Emissivity , Heat , Natural convection , Temperature , Storage , Water , Welding

Case Study of Certification of Small Quantities of RAM: Comparison With SGQ Concept

Glenn Abramczyk, James Shuler, Steven J. Nathan, Allen C. Smith

PVP 2011; 377-380https://doi.org/10.1115/PVP2011-57666

Abstract

View Articletitled, Case Study of Certification of Small Quantities of RAM: Comparison With SGQ Concept

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Topics: Containment , Containment vessels , Hazardous substances , Hazards , Helium , Packaging , Photons , Radiation (Physics) , Radioactive substances

Dynamic Structural Analysis of the Model 9979 Type AF Shipping Packaging

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

PVP 2011; 381-386https://doi.org/10.1115/PVP2011-57688

Abstract

View Articletitled, Dynamic Structural Analysis of the Model 9979 Type AF Shipping Packaging

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Topics: Packaging , Structural analysis , Accidents , Corners (Structural elements) , Damage , Deformation , Engineering prototypes , Finite element analysis , Regulations , Rivers

Development of Tritium Transport Package for ITER Supply

Sanghoon Lee, Min-Soo Lee, Ju-Chan Lee, Woo-Seok Choi, Ki-Seog Seo

PVP 2011; 387-393https://doi.org/10.1115/PVP2011-57851

Abstract

View Articletitled, Development of Tritium Transport Package for ITER Supply

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Topics: Transport packages , Storage , Aluminum , Containment vessels , Vessels , Accidents , Containment , Fusion reactors , Nuclear power , Pressure

Implementation of the ASME Code and NQA-1 in U.S. Department of Energy Packaging Certification Program Training Courses

Lawrence F. Gelder

PVP 2011; 395-398https://doi.org/10.1115/PVP2011-57882

Abstract

View Articletitled, Implementation of the ASME Code and NQA-1 in U.S. Department of Energy Packaging Certification Program Training Courses

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Topics: ASME Standards , Packaging , Safety , Design , Radioactive substances , Transportation systems , Boilers , Pressure vessels

Severe Transportation Accidents: Do Used Nuclear Fuel Transportation Packages Survive Real World Accidents?

Christopher S. Bajwa, Earl P. Easton, Harold Adkins, Judith Cuta, Nicholas Klymyshyn, Sarah Suffield

PVP 2011; 399-411https://doi.org/10.1115/PVP2011-57999

Abstract

View Articletitled, Severe Transportation Accidents: Do Used Nuclear Fuel Transportation Packages Survive Real World Accidents?

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Topics: Accidents , Nuclear fuels , Transport packages , Transportation systems , Fire , Overpasses , Collapse , Gasoline , Tankers , Trucks

Used Nuclear Fuel Transportation Package Seal Performance in Beyond Design Basis Thermal Conditions

Felix Gonzalez, Christopher Bajwa, Robert Einziger, Earl Easton, Jiann Yang, Edward Hnetkovsky

PVP 2011; 413-420https://doi.org/10.1115/PVP2011-58000

Abstract

View Articletitled, Used Nuclear Fuel Transportation Package Seal Performance in Beyond Design Basis Thermal Conditions

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Topics: Design , Nuclear fuels , Transport packages , Temperature , National Institute of Standards and Technology , Testing , Fire , Accidents , Containment , Flanges

Road Tunnels and Fires: Implications for the Transport of Used Nuclear Fuel

E. Easton, C. Bajwa, T. Mintz, J. Huczek, K. Das, K. Axler

PVP 2011; 421-427https://doi.org/10.1115/PVP2011-58001

Abstract

View Articletitled, Road Tunnels and Fires: Implications for the Transport of Used Nuclear Fuel

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Topics: Fire , Nuclear fuels , Roads , Tunnels , Accidents , Trucks , Chain , Concrete walls , Maintenance , Modeling

Thermal Modeling Analysis of SRS 70 Ton Cask

S. Y. Lee, J. M. Jordan, S. J. Hensel

PVP 2011; 429-437https://doi.org/10.1115/PVP2011-58031

Abstract

View Articletitled, Thermal Modeling Analysis of SRS 70 Ton Cask

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Topics: Computational fluid dynamics , Electrical measurement , Fuels , Heat , Heat transfer , Manufacturing , Melting , Modeling , Modeling analysis , National Institute of Standards and Technology