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

Topics: Fatigue , Nuclear power stations , Stress , Coolants , Finite element methods , Flow (Dynamics) , Monitoring systems , Pipes , Pressure , Pressurized water reactors

Operations and Maintenance of Pressure Vessels, Heat Exchangers and Structures

The Reliability Investigation on the Assessment Criteria for Local Metal Loss Based on API 579-1/ASME FFS-1

Takuyo Kaida, Yuichi Mogami, Satoshi Izumi, Shinsuke Sakai

PVP 2010; 29-36doi:https://doi.org/10.1115/PVP2010-25120

Abstract

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Topics: American Petroleum Institute , Fitness-for-service , Metals , Reliability , Safety , Modeling

Effect of Hot Feed Injection Time on Thermal Fatigue Life of Shell-to-Skirt Junction Area of Coke Drums

Masaaki Oka, Himsar Ambarita, Kenichi Kawashima, Masashi Daimaruya

PVP 2010; 37-43doi:https://doi.org/10.1115/PVP2010-25183

Abstract

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Topics: Coke , Fatigue life , Junctions , Shells , Cycles , Fracture (Materials) , Fracture (Process) , Finite element methods , Finite element model , Dimensions

Fracture Toughness of Pressure Boundary Steels With Higher Yield Strength

Karan K. Gupta, Christopher L. Hoffmann, Andrew M. Hamilton, Frank DeLose

PVP 2010; 45-58doi:https://doi.org/10.1115/PVP2010-25214

Abstract

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Topics: Fracture toughness , Pressure , Steel , Yield strength , Heat , Metals , Forgings (Products) , Fracture (Materials) , Boilers , Forging

Guide for Applying Codes and Standards for Safe Operation and Maintenance of Pressure Equipment in Refinery and Petrochemical Services

John Reynolds

PVP 2010; 59-63doi:https://doi.org/10.1115/PVP2010-25220

Abstract

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Topics: Engineering standards , Maintenance , Petrochemicals , Pressure equipment , Construction , American Petroleum Institute , Chemical processes , Corrosion , In-service inspection , Inspection

Measurement of Pressure Loss Throughout a Clogged Steam Generator Tube Support Plate in Single Phase Flow

Olivier Brunin, Geoffrey Deotto, Franck David, Joe¨l Pillet, Gilles Dague, Alexandre Nicoli

PVP 2010; 65-72doi:https://doi.org/10.1115/PVP2010-25606

Abstract

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Topics: Boilers , Flow (Dynamics) , Pressure , Plates (structures) , Two-phase flow , Refrigerants , Water , Computation , Computational methods , Heat

Installation of Serrated Metal Core Without Full Disassembly of a Heat Exchanger

Russ Currie, R. Davis

PVP 2010; 73-80doi:https://doi.org/10.1115/PVP2010-25685

Abstract

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Topics: Heat exchangers , Metals , Corrosion , Flanges , Inspection , North Sea , Sealing (Process)

Weld Repair for Pressure Vessels Made From Cr-Mo Steels

Rinzo Kayano, Eiichi Yamamoto, Takayasu Tahara

PVP 2010; 81-88doi:https://doi.org/10.1115/PVP2010-25971

Abstract

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Topics: Maintenance , Pressure vessels , Steel , Welding , Hydrogen , Damage , Embrittlement , Petroleum , Pressure equipment , Chemical industry

Fault Analysis of Above Ground Oil Storage Tank Leakage Accident

Haruki Nishi, Tatsuya Suzuka, Kota Suzuki

PVP 2010; 89-94doi:https://doi.org/10.1115/PVP2010-26026

Abstract

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Topics: Accidents , Leakage , Storage tanks , Pumps , Pipelines , Pressure , Failure , Brittle fracture , Fractography , Pipes

Strain Rate Evaluation of Some Typical Nuclear Power Plant Components During Plant Operation

Koji Dozaki, Hiromasa Chitose, Hiroshi Ogawa, Hideo Machida

PVP 2010; 95-101doi:https://doi.org/10.1115/PVP2010-26086

Abstract

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Topics: Boiling water reactors , Design , Dynamic testing (Materials) , Evaluation methods , Failure , Failure mechanisms , Fatigue , Fatigue life , Finite element methods , Nuclear power stations

Effects of Initial Tube-Tubesheet Clearance and Grooves on Axial and Hoop Residual Stresses of Roller Expanded Joints

A. N. Shuaib, O. M. Duffuaa, N. Merah, Y. Al-Nassar

PVP 2010; 103-110doi:https://doi.org/10.1115/PVP2010-26156

Abstract

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Topics: Clearances (Engineering) , Residual stresses , Rollers , Stress , Hoop stress , Deformation , Finite element model , Fracture (Materials) , Stress corrosion cracking

An Analysis of a Completed Temper Bead Weld Repair Performed on an Amine Tower

William C. Mohr, Matt A. Boring, Yu-Ping Yang

PVP 2010; 111-119doi:https://doi.org/10.1115/PVP2010-26168

Abstract

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Topics: Maintenance , Welding , American Petroleum Institute , Heat , Vessels , Residual stresses , Steel , Stress , Annulus , ASME Boiler and Pressure Vessel Code

Piping and Piping Supports

Advanced Methods for Vibration Reduction at a Piping

Klaus Kerkhof, Joachim Schwenkkros, Frank Barutzki, Christa Gurr-Beyer

PVP 2010; 123-132doi:https://doi.org/10.1115/PVP2010-25603

Abstract

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Topics: Pipes , Vibration , Vibration absorbers , Design , Piping systems , Risk reduction , Steel construction , Stress , Dampers , Emergencies

Plant Life Extension: Aging and Life Management

Variation of Plant Electrical Output Due to Main Steam Temperature and Thermal Power

D. W. Yoon, C. K. Park, B. H. Lee, K. C. Jeong

PVP 2010; 135-140doi:https://doi.org/10.1115/PVP2010-25112

Abstract

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Topics: Steam , Temperature , Thermal energy , Cycles , Heat , Power stations , Pressure , Thermal efficiency , Turbines , Condensers (steam plant)

Integrity Management of Aged Equipment in Sour Oil and Gas Service: Kuwait Oil Company Approach

Abdul Wahab Al-Mithin, Abdul Wahab Al-Ahmad, Vinayak Sardesai, G. Santhosh Kumar

PVP 2010; 141-147doi:https://doi.org/10.1115/PVP2010-25115

Abstract

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Topics: Coating processes , Coatings , Fluids , Gas industry , Hydrogen , Inspection , Life extension , Materials degradation , Pressure vessels , Vessels

Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics

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

PVP 2010; 149-155doi:https://doi.org/10.1115/PVP2010-25195

Abstract

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Topics: Boiling water reactors , Fracture mechanics , Pressure vessels , Welded joints , Probability , Failure , Fluence (Radiation measurement) , Licensing , Life extension , Neutrons

Probabilistic Fracture Analysis for Boiling Water Reactor Pressure Vessels Subjected to Low Temperature Over-Pressure Event

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

PVP 2010; 157-164doi:https://doi.org/10.1115/PVP2010-25196

Abstract

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Topics: Boiling water reactors , Fracture (Materials) , Fracture (Process) , Low temperature , Pressure , Pressure vessels , In-service inspection , Welded joints , Safety , Failure

Reconstitution of Reactor Pressure Boundary Components Design Stress Report for License Renewal

Kirby Woods, Kenneth Thomas

PVP 2010; 165-171doi:https://doi.org/10.1115/PVP2010-25215

Abstract

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Topics: Design , Licensing , Pressure , Stress , Cycles , Nuclear power stations , ASME Standards , Composite materials , Elasticity , Electricity (Physics)

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

Tyler D. Novotny, Terry J. Herrmann, George V. Mileris, Raymond M. Pace

PVP 2010; 173-179doi:https://doi.org/10.1115/PVP2010-25329

Abstract

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Topics: Boiling water reactors , Fatigue , Licensing , Design , Transients (Dynamics) , Computers , Fatigue analysis , Nuclear power stations , Public utilities , Safety

The Function Test for the Reliability Confirmation of High Temperature and High Pressure Vessel for Irradiation

Kook-Nam Park, Jong-Min Lee, Sung-Ho Ahn, Sang-Ik Wu, Young-Ki Kim

PVP 2010; 181-187doi:https://doi.org/10.1115/PVP2010-25388

Abstract

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Topics: High temperature , High-pressure vessels , Irradiation (Radiation exposure) , Reliability , Fuels , Pipes , Pressure , Leakage , Pressure vessels , Pressurized water reactors

Comparison of PWSCC Growth Analysis With Field Data of Japanese PWR Plants

Seiji Asada, Harutaka Suzuki, Shinro Hirano, Shoji Sato, Kenji Matsumoto, Kouji Dozaki

PVP 2010; 189-193doi:https://doi.org/10.1115/PVP2010-25526

Abstract

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Topics: Pressurized water reactors , Fracture (Materials) , Alloys , Japan Society of Mechanical Engineers , Nozzles , Welded joints , Energy generation , Metals , Nuclear power , Safety

ARCMAC Optical Creep Monitoring: Developments in Image Analysis Techniques and Creep Measurement Validation

Andy Morris, Iain Palmer, Chris Maharaj, John Dear

PVP 2010; 195-202doi:https://doi.org/10.1115/PVP2010-25617

Abstract

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Topics: Creep , Image processing , Pipes , Failure , Gages , High temperature , Image formation , Lenses (Optics) , Power stations , Resolution (Optics)

Long Term Operation and Surveillance Specimen Program of WWER RPVs

Milan Brumovsky, Milos Kytka

PVP 2010; 203-209doi:https://doi.org/10.1115/PVP2010-25620

Abstract

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Topics: Surveillance , Design , Embrittlement , Irradiation (Radiation exposure) , Life extension , Nuclear power stations , Reactor vessels , Temperature , Testing

CFD Tools for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Thermalhydraulic Benchmark on the Validation Test Case UPTF

A. Martin, F. Huvelin, G. Balard, S. Bellet, B. Durand, P. Martinez

PVP 2010; 211-220doi:https://doi.org/10.1115/PVP2010-25646

Abstract

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Topics: Computational fluid dynamics , Pressure , Reactor vessels , Thermal shock

Asset Management Methodology: A Probabilistic Approach to Optimize Investments for Coal-Fired Power Plants Reheaters

Ludovic Benetrix, Pierre Bertrand

PVP 2010; 221-227doi:https://doi.org/10.1115/PVP2010-25692

Abstract

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Topics: Coal , Power stations , Failure , Air pollution control , Boilers , Economic analysis , Electric power generation , Feedback , Modeling , Nuclear power stations

Heavy Components Replacement in Nuclear Power Plants: Guidelines and Experiences

Ki Sig Kang

PVP 2010; 229-235doi:https://doi.org/10.1115/PVP2010-25875

Abstract

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Topics: Nuclear power stations , Pressurized water reactors , Pipes , Reactor vessels , Boilers , Boiling water reactors , Fatigue , Heavy water reactors , Nuclear power , Nuclear reactor coolants

Steam Generator Replacement at San Onofre Nuclear Generating Station Unit 2

James K. Chan, David J. Calhoun

PVP 2010; 237-245doi:https://doi.org/10.1115/PVP2010-25897

Abstract

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Topics: Boilers , Power stations , Design

Managing Environmental Fatigue of the Real Components in a PWR

Horst Rothenho¨fer, Gu¨nter Ko¨nig

PVP 2010; 247-254doi:https://doi.org/10.1115/PVP2010-25979

Abstract

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Topics: Fatigue , Pressurized water reactors , Stress , Cycles , Design , Light water reactors , Nuclear power stations , Sprays , Surges

Determining the Onset of Stress Corrosion Cracking in Austenitic Stainless Steel With Permeability Change

Bob Lisowyj, Zoran Kuljis

PVP 2010; 255-261doi:https://doi.org/10.1115/PVP2010-25984

Abstract

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Topics: Permeability , Stainless steel , Stress corrosion cracking , Eddies (Fluid dynamics) , Eddy currents (Electricity) , Nuclear power stations , Pressurized water reactors , Signals , Calibration , Cracking (Materials)

Flamanville 3 EPR: How to Define the Pre-Service NDE Inspection Program

F. Champigny, P. Blin, J. L. Guilloteau

PVP 2010; 263-270doi:https://doi.org/10.1115/PVP2010-26000

Abstract

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Topics: Inspection , Nondestructive evaluation , Coolants , Fatigue , Fracture (Materials) , Fracture (Process) , In-service inspection , Pressurized water reactors , Rivers

U.S. License Renewal and Long Term Operation in the 2010’s

Garry G. Young

PVP 2010; 271-275doi:https://doi.org/10.1115/PVP2010-26046

Abstract

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Topics: Licensing , Nuclear power stations , Electric power generation , Nuclear power plant operations , Reliability

Application of Aging Management Strategies for Reactor Vessel Internals and Core Support Structures

Tama´s R. Liszkai, Matthew Snyder, Steve Fyfitch, Hongqing Xu, Hasan Charkas

PVP 2010; 277-286doi:https://doi.org/10.1115/PVP2010-26137

Abstract

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Topics: Reactor vessels , Alloys , Inspection , Pressurized water reactors , Licensing , Acceptance criteria , Design , Failure , Nondestructive evaluation , Public utilities

Pumps and Valves

ASME Section III Treatment of Stress Distribution in Cylindrical Vessels With Symmetric Thin-Walled Discontinuity

L. Ike Ezekoye, Gerald A. Riegel, David Ristau, Richard Way

PVP 2010; 289-296doi:https://doi.org/10.1115/PVP2010-25987

Abstract

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Topics: Stress concentration , Vessels , Design , Stress , Rupture , Finite element analysis , Pressure , Valves , Actuators , ASME Standards

Analysis of Contact Pressure Distribution on a Pass Partition Gasket in Conjunction With a Double-Tapered Seal in a High Pressure Heat Exchanger Closure

Christopher Gardner, Rajeev Madazhy, Erik Howard

PVP 2010; 297-303doi:https://doi.org/10.1115/PVP2010-26157

Abstract

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Topics: Gaskets , Heat exchangers , High pressure (Physics) , Pressure , Finite element analysis , Leakage , Manufacturing , Design , Diaphragms (Mechanical devices) , Diaphragms (Structural)

Regulations, Codes, and Standards

Regulatory Issues Associated With Shipment of Small Quantities of Radioactive Material

Allen C. Smith, Glenn A. Abramczyk, Stephen J. Nathan

PVP 2010; 307-314doi:https://doi.org/10.1115/PVP2010-25142

Abstract

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Topics: Radioactive substances , Containment , Containment vessels , Engineering standards , Leakage , Radiation (Physics) , Radioisotopes , Ships

Development of Burn Test Specifications for Fire Protection Materials in RAM Packages

Allen C. Smith, Narendra K. Gupta, Paul S. Blanton

PVP 2010; 315-319doi:https://doi.org/10.1115/PVP2010-25337

Abstract

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Topics: Fire , Testing , Insulation , Fire testing , Thermal properties , Accidents , Design , Radioactive substances , Regulations , Temperature

Authorizing the DOT Specification 6M Packaging for Continued Use at the Savannah River Site

Robert W. Watkins, Bradley M. Loftin, Don S. Hoang

PVP 2010; 321-324doi:https://doi.org/10.1115/PVP2010-25437

Abstract

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Topics: Packaging , Rivers , Radioactive substances , Regulations , Transportation systems , Safety , Hazardous substances

Safety, Reliability, and Risk Assessment

Review of Proposed Methodology for Risk-Informed Relaxation to ASME Section XI: Appendix G

Terry Dickson, Eric Focht, Mark Kirk

PVP 2010; 327-337doi:https://doi.org/10.1115/PVP2010-25010

Abstract

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Topics: Relaxation (Physics) , Risk , Regulations , Reactor vessels , Transients (Dynamics) , ASME Standards , Heat , Boundary-value problems , Embrittlement , Failure

Safety Assessment of Reactor Pressure Vessel Integrity for Loss of Coolant Accident Conditions

D. Beukelmann, W. Guo, W. Holzer, R. Kauer, W. Mu¨nch, C. Reichel, P. Scho¨ner

PVP 2010; 339-348doi:https://doi.org/10.1115/PVP2010-25049

Abstract

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Topics: Accidents , Coolants , Reactor vessels , Safety , Stress , Temperature , Temperature distribution , Computational fluid dynamics , Corners (Structural elements) , Finite element analysis

Failure Frequency Estimates for Boiling Water Reactor Pressure Vessels

F. A. Simonen, S. R. Gosselin, J. E. Rhoads, A. T. Chiang

PVP 2010; 349-361doi:https://doi.org/10.1115/PVP2010-25232

Abstract

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Topics: Boiling water reactors , Failure , Pressure vessels , Vessels , Rupture , Pressurized water reactors , Accidents , Damage , Accounting , Containment systems

Hydrodynamic Forces, Pressure and Mass Flux in Two-Phase Air-Water Flow Through Transparent Safety Valve Model

Vasilios Kourakos, Sai¨d Chabane, Patrick Rambaud, Jean-Marie Buchlin

PVP 2010; 363-370doi:https://doi.org/10.1115/PVP2010-25440

Abstract

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Topics: Flow (Dynamics) , Fluid-dynamic forces , Pressure , Safety , Transparency , Valves , Water , Disks , Chemical industry , Design

Probabilistic Leak-Before-Break Assessment of a Main Coolant Line

Igor Varfolomeev, Denis Ivanov, Dieter Siegele, Gerhard Nagel

PVP 2010; 371-378doi:https://doi.org/10.1115/PVP2010-25676

Abstract

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Topics: Coolants , Leak-before-break , Fracture (Materials) , Probability , Failure , Fatigue cracks , Cladding systems (Building) , Fracture mechanics , Nuclear power stations , Pipes

Towards an Improved Understanding of Water-Hammer Column-Separation Due to Rapid Valve Closure

H. A. Warda, Y. Elashry

PVP 2010; 379-395doi:https://doi.org/10.1115/PVP2010-26146

Abstract

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Topics: Separation (Technology) , Valves , Water hammer , Cavities , Collapse , Pipes , Pressure , Pumps , Vapors , Computer simulation

Toxic Substances: Transportation and Storage of Radioactive Materials

Thermal Performance of Radioactive Material (RAM) Packages in Transport Configuration

Narendra K. Gupta

PVP 2010; 399-405doi:https://doi.org/10.1115/PVP2010-25017

Abstract

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Topics: Radioactive substances , Vehicles , Containment vessels , Cushioning materials , Heat , Packaging , Regulations , Safety , Security

Dynamic Structural Analysis of the 9516 Transport Package

Zenghu Han, Vikram N. Shah, Jeries Abou-Hanna, Yung Y. Liu

PVP 2010; 407-414doi:https://doi.org/10.1115/PVP2010-25047

Abstract

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Topics: Accidents , ASME Boiler and Pressure Vessel Code , Bearings , Computers , Containment vessels , Cushioning materials , Finite element analysis , Mechanical engineering , Model validation , Steel

Effects of Moisture in the 9975 Shipping Package Fiberboard Assembly

W. L. Daugherty, K. A. Dunn, J. L. Murphy, E. R. Hackney

PVP 2010; 415-420doi:https://doi.org/10.1115/PVP2010-25087

Abstract

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Topics: Fiberboard (Engineered wood) , Manufacturing , Paperboard , Storage , Absorption , Compacting , Equilibrium (Physics) , Insulation , Rivers , Transportation systems

Thermal Analysis of Geologic High-Level Radioactive Waste Packages

S. Y. Lee, S. J. Hensel, C. De Bock

PVP 2010; 421-432doi:https://doi.org/10.1115/PVP2010-25105

Abstract

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Topics: Computational fluid dynamics , Radioactive wastes , Thermal analysis , Temperature , Transients (Dynamics) , Convection , Cooling , Design , Emissivity , Engineering design

Long-Term Leak Tightness of O-Ring Seals in the 9975 Shipping Package

Elizabeth N. Hoffman, T. Eric Skidmore, William L. Daugherty

PVP 2010; 433-438doi:https://doi.org/10.1115/PVP2010-25106

Abstract

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Topics: Leakage , Seals , Service life (Equipment) , Temperature , Testing , Compressive stress , Containment vessels , Failure , Relaxation (Physics) , Storage

Aging Model for Cane Fiberboard Overpack in the 9975 Shipping Package

W. L. Daugherty, S. P. Harris

PVP 2010; 439-447doi:https://doi.org/10.1115/PVP2010-25118

Abstract

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Topics: Fiberboard (Engineered wood) , Paperboard , Radioactive substances , Storage , Temperature , Thermal insulation

Evaluation of Torque vs. Closure Bolt Preload for a Typical Containment Vessel Under Service Conditions

Allen C. Smith

PVP 2010; 449-456doi:https://doi.org/10.1115/PVP2010-25135

Abstract

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Topics: Containment vessels , Torque , Radioactive substances , Stress , Design , Fasteners , Pressure , Uncertainty , Vibration

9975 Shipping Package: Performance of Alternate Materials for Long-Term Storage Application

T. E. Skidmore, W. L. Daugherty, E. N. Hoffman

PVP 2010; 457-465doi:https://doi.org/10.1115/PVP2010-25279

Abstract

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Topics: Storage , Construction , Fiberboard (Engineered wood) , Paperboard , Seals , Rivers , Softwood (Wood product) , Testing

Packaging and Transportation of Additional Neptunium Oxide

Robert W. Watkins, Stephen J. Hensel, Jeffrey M. Jordan

PVP 2010; 467-470doi:https://doi.org/10.1115/PVP2010-25438

Abstract

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Topics: Packaging , Transportation systems , Containers , Rivers , Safety

Historical Rail Accident Analyses Identifying Accident Parameters That Could Impact Transportation of Spent Nuclear Fuel

Todd S. Mintz, George Adams, Marius Necsoiu, James Mancillas, Chris Bajwa, Earl Easton

PVP 2010; 471-481doi:https://doi.org/10.1115/PVP2010-25445

Abstract

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Topics: Accidents , Rails , Spent nuclear fuels , Transportation systems , Fire , Hazardous substances , Transport packages , Trains , Pipelines , Railroads

Drop Tests Results of Revised Closure Bolt Configuration of the Standard Waste Box, Standard Large Box-2, and Ten Drum Overpack Packagings

Cecil G. May, Charles A. McKeel, Erich K. Opperman

PVP 2010; 483-495doi:https://doi.org/10.1115/PVP2010-25449

Abstract

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Topics: Packaging , Pressure , Radioactive substances , Rivers , Stress , Testing

Modeling Heat Transfer in Spent Fuel Transfer Cask Neutron Shields: A Challenging Problem in Natural Convection

James A. Fort, Judith M. Cuta, Chris S. Bajwa, Emilio Baglietto

PVP 2010; 497-506doi:https://doi.org/10.1115/PVP2010-25752

Abstract

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Topics: Heat transfer , Modeling , Natural convection , Neutrons , Spent nuclear fuels , Computational fluid dynamics , Steady state , Radiation (Physics) , Annulus , Engineering simulation

Package Impact Models as a Precursor to Cladding Analysis

Nicholas A. Klymyshyn, Harold E. Adkins, Christopher S. Bajwa, Jason M. Piotter

PVP 2010; 507-513doi:https://doi.org/10.1115/PVP2010-25773

Abstract

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Topics: Cladding systems (Building) , Fuels , Accidents , Finite element model , Manufacturing , Modeling , Safety , Spent fuel storage , Structural dynamics , Transport packages

The Potential Impacts of Recent Transportation Accidents Involving Severe Fires on the Safe Shipment of Spent Nuclear Fuel

Christopher S. Bajwa, Earl P. Easton

PVP 2010; 515-522doi:https://doi.org/10.1115/PVP2010-25852

Abstract

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Topics: Accidents , Fire , Spent nuclear fuels , Transportation systems , Tunnels , Overpasses , Chain , Collapse , Concrete walls , Flames

A Method for the Coupled Thermal-Structural Analysis of Radioactive Material Shipping Packages in Hypothetical Accident Conditions: Part 1—NCT Thermal Load and Some HAC Mechanical Loads

Tsu-te Wu, Narendra K. Gupta, Allen C. Smith, Paul S. Blanton

PVP 2010; 523-530doi:https://doi.org/10.1115/PVP2010-25956

Abstract

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Topics: Accidents , Radioactive substances , Stress , Damage , Design , Fire , Modeling , Packaging , Regulations , Structural analysis

Use of Geometrically-Accurate Models to Predict Spent Nuclear Fuel Cladding Temperatures Within a Truck Cask Under Normal and Fire Accident Conditions

Krishna Kumar Kamichetty, Miles Greiner, Venkata V. R. Venigalla

PVP 2010; 531-541doi:https://doi.org/10.1115/PVP2010-25991

Abstract

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Topics: Accidents , Cladding systems (Building) , Fire , Spent nuclear fuels , Temperature , Trucks , Engineering simulation , Simulation , Computational fluid dynamics , Fuels

A Comparison of Two Thermal Insulation and Structural Materials for Use in Type B Packagings

Paul S. Blanton, Kurt R. Eberl, Paul T. Mann

PVP 2010; 543-550doi:https://doi.org/10.1115/PVP2010-26048

Abstract

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Topics: Accidents , Ceramic fibers , Ceramics , Containment vessels , Design , Engineering prototypes , Fire , Heat , Insulation , Manufacturing

Prediction of Closure Bolt Loads in Small Pressure Vessels: NUREG/CR-6007 vs. Detailed Finite Element Analysis

Charles A. McKeel

PVP 2010; 551-555doi:https://doi.org/10.1115/PVP2010-26065

Abstract

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Topics: Finite element analysis , Pressure vessels , Stress , Pressure , Containment vessels , Shapes

Effects of Package Content Position on Slap-Down Angle

Charles A. McKeel

PVP 2010; 557-560doi:https://doi.org/10.1115/PVP2010-26067

Abstract

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Topics: Accidents , Dynamics (Mechanics) , Engineers , Regulations

Validation of Container Analysis Fire Environment (CAFE) Code for Memorial Tunnel Fire Ventilation Test Program

N. R. Chalasani, Miles Greiner, Ahti Suo-Anttila

PVP 2010; 561-571doi:https://doi.org/10.1115/PVP2010-26075

Abstract

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Topics: Containers , Fire , Tunnels , Ventilation , Gates (Closures) , Temperature , Engineering simulation , Flow (Dynamics) , Simulation , Air flow

Preshipment Leak Testing of 9977 Containment Vessels With the TM Electronics Solution Model S1A-L2-V Leak Tester

Donald J. Trapp

PVP 2010; 573-577doi:https://doi.org/10.1115/PVP2010-26095

Abstract

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Topics: Containment vessels , Electronics , Leakage , Testing , Rivers , Pacific Ocean , Pressure , Roads , Seals , Testing equipment

Thermal Analysis of a Proposed Transport Cask for Three Advanced Burner Reactor Used Fuel Assemblies

Tim Bullard, Miles Greiner, Matt Dennis, Samuel Bays, Ruth Weiner

PVP 2010; 579-586doi:https://doi.org/10.1115/PVP2010-26138

Abstract

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Topics: Fuels , Thermal analysis , Engineering simulation , Neutrons , Simulation , Temperature , Cladding systems (Building) , Temperature profiles , Composite materials , Computational fluid dynamics

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Operations and Maintenance of Pressure Vessels, Heat Exchangers and Structures

Piping and Piping Supports

Plant Life Extension: Aging and Life Management

Pumps and Valves

Regulations, Codes, and Standards

Safety, Reliability, and Risk Assessment

Toxic Substances: Transportation and Storage of Radioactive Materials

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