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

Topics: Creep , Heat treating (Metalworking) , Stress , Welded joints , Pressure , Welding , High temperature , Boiler tubes , Finite element analysis , Design

Generating Confidence in Inspection Results

R. V. Booler, W. L. Daniels, J. P. Taggart

PVP 2009; 9-13doi:https://doi.org/10.1115/PVP2009-78052

Abstract

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Topics: Inspection , Nondestructive evaluation , Safety , Engineering disciplines , Acceptance criteria , Life extension , Nuclear industry , Probability , Risk-based inspection , Uncertainty

Tearing Resistance Properties of Stainless Steel Orbital TIG Narrow Gap Welds of Primary Piping in PWR Plants

Pascal Ould, Pierre Joly, Sylvain Pillot

PVP 2009; 15-23doi:https://doi.org/10.1115/PVP2009-78077

Abstract

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Topics: Pipes , Pressurized water reactors , Stainless steel , Welded joints , Coolants , Butt welding , Electrodes , Mechanical properties , Metals , Safety

Reliability of Onsite Emergency Power for the New Generation and Advanced Nuclear Power Plants

Mansoor H. Sanwarwalla

PVP 2009; 25-29doi:https://doi.org/10.1115/PVP2009-78127

Abstract

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Topics: Emergency power , Nuclear power stations , Reliability , Design , Batteries , Boiling water reactors , Diesel , Energy generation , High temperature , Maintenance

Monitoring, Diagnostics and Inspection

Extending the Internal Examination Intervals for Pressure Vessels Using an RBI Approach

Philippa Moore, John Wintle

PVP 2009; 33-40doi:https://doi.org/10.1115/PVP2009-77196

Abstract

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Topics: Containment , Environmental health and safety , Failure , Hazards , Health and safety , Inspection , Petrochemicals , Pressure equipment , Pressure vessels , Risk

Dynamic Response of the WWER 1000/320 Reactor on the Pressure Pulsations Generated by Main Circulation Pumps

Ladislav Pecinka, Petr Stulik, Vladimir Zeman

PVP 2009; 41-44doi:https://doi.org/10.1115/PVP2009-77304

Abstract

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Topics: Dynamic response , Pressure , Pumps , Blades , Boundary layers , Computer simulation , Pressurized water reactors , Rotors , Sound pressure , Turbulence

Estimating ASME Section III and VIII Heat Exchanger Nozzle Loads

L. Ike Ezekoye, Colin Arnold

PVP 2009; 45-52doi:https://doi.org/10.1115/PVP2009-77829

Abstract

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Topics: Heat exchangers , Nozzles , Stress , Design , Acceptance criteria , Geometry , Heat , Materials properties , Pipes , Power stations

An Integrated Approach for Monitoring Gas Accumulation in Safety Related Systems

L. Ike Ezekoye, Ryan D. Griffin, William M. Turkowski, Gregory R. Williams

PVP 2009; 53-60doi:https://doi.org/10.1115/PVP2009-77957

Abstract

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Topics: Safety , Pumps , Design , Pipes , Emergency core cooling systems , Gases , Containment , Damage , Flow (Dynamics) , Heat

Toxic Substances: Storage and Transportation

Radiation Heat Transfer Environment in Fire and Furnace Tests of Radioactive Materials Packages

Allen C. Smith

PVP 2009; 63-71doi:https://doi.org/10.1115/PVP2009-77017

Abstract

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Topics: Fire , Furnaces , Heat transfer , Radiation (Physics) , Radioactive substances , Emissivity , Fuels , Temperature , Accidents , Flames

Thermal Analysis of Drum Type Radioactive Material (RAM) Packaging Arrays in Storage

Narendra K. Gupta

PVP 2009; 73-79doi:https://doi.org/10.1115/PVP2009-77045

Abstract

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Topics: Packaging , Radioactive substances , Storage , Thermal analysis , Containment vessels , Cushioning materials , Design , Heat , Leakage , Regulations

Security in the Transport of Radioactive Materials

Ronald B. Pope, Richard R. Rawl

PVP 2009; 81-89doi:https://doi.org/10.1115/PVP2009-77089

Abstract

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Topics: Radioactive substances , Security , Nuclear power , Safety , Training programs , Transportation systems

Strain-Based Acceptance Criteria for Energy-Limited Events

Spencer D. Snow, Dana K. Morton, Edward L. Pleins, Robert Keating

PVP 2009; 91-96doi:https://doi.org/10.1115/PVP2009-77122

Abstract

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Topics: Acceptance criteria , Design , Stress , Boilers , Design methodology , Displacement , Failure , Mechanical engineers , Pressure vessels , Radioactive substances

Packaging and Transportation of Neptunium Oxide

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

PVP 2009; 97-99doi:https://doi.org/10.1115/PVP2009-77200

Abstract

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

Burn Behavior of a Polyurethane Foam Impact Limiter

Jie Li, Shiu-Wing Tam, Yung Y. Liu

PVP 2009; 101-108doi:https://doi.org/10.1115/PVP2009-77261

Abstract

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Topics: Cushioning materials , Urethane foam , Temperature , Flames , Combustion , Containment , Fuels , Gases , Pyrolysis , Design

A Radiofrequency Identification (RFID) Temperature-Monitoring System for Extended Maintenance of Nuclear Materials Packaging

Kun Chen, Hanchung Tsai, Bud Fabian, Yung Liu, James Shuler

PVP 2009; 109-115doi:https://doi.org/10.1115/PVP2009-77265

Abstract

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Topics: Maintenance , Packaging , Temperature , Seals , Computer software , Containment , Leakage , Transportation systems , Databases , Heat

Operational Readiness of the ES-3100 Type B Shipping Container for Fissile Materials

Jeffrey G. Arbital, Kenneth E. Sanders

PVP 2009; 117-124doi:https://doi.org/10.1115/PVP2009-77416

Abstract

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Topics: Containers , Licensing , Radioactive substances , Transportation systems

An Analytical Method of Determining Damage Initiation for Potential Use in Establishing Strain-Based Failure Criteria

Tsu-te Wu

PVP 2009; 127-136doi:https://doi.org/10.1115/PVP2009-77435

Abstract

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Topics: Damage , Failure , Stress , Ductile fracture , Shear (Mechanics) , Computer simulation , Displacement , Fracture (Materials) , Fracture (Process) , Load bearing capacity

Dynamic Analysis of Shipping Cask Subjected to Sequential Bolt Preload and Impact Loads

Tsu-te Wu

PVP 2009; 137-144doi:https://doi.org/10.1115/PVP2009-77438

Abstract

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Topics: Dynamic analysis , Stress , Dynamic response , Finite element analysis , Structural response analysis

Severe Transportation Accidents: Impacts of Severe Fires on Radioactive Material Transportation

Christopher S. Bajwa, Earl P. Easton, Darrell S. Dunn

PVP 2009; 145-158doi:https://doi.org/10.1115/PVP2009-77790

Abstract

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Topics: Accidents , Fire , Radioactive substances , Transportation systems , Overpasses , Collapse , Flames , Gasoline , Spent nuclear fuels , Structural steel

Potential Effects of Historic Rail Accidents on the Integrity of Spent Nuclear Fuel Transportation Packages

Christopher S. Bajwa, Earl P. Easton

PVP 2009; 159-165doi:https://doi.org/10.1115/PVP2009-77811

Abstract

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Topics: Accidents , Rails , Spent nuclear fuels , Transport packages , Fire , Hazardous substances , Radioactive substances , Regulations

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

Reference Stresses for Cold-Tube-Bends Including Thickness Variation and Ovality Using Three-Dimensional Finite Element Method

Khosrow Zarrabi, Felix Kumiadi Kwok

PVP 2009; 169-174doi:https://doi.org/10.1115/PVP2009-77004

Abstract

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Topics: Collapse , Finite element methods , Stress

Confirmation of Validity of Hot Tapping Welding

Yasushi Ogayu

PVP 2009; 175-179doi:https://doi.org/10.1115/PVP2009-77072

Abstract

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Topics: Welding , Pipes , Thermal analysis , Base metals , Pressure , Temperature , Computer simulation , Cooling , Finite element analysis , Heat

Loads Applied to Clogged Steam Generators Internal Structures

Olivier Brunin, Geoffrey Deotto

PVP 2009; 181-190doi:https://doi.org/10.1115/PVP2009-77140

Abstract

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Topics: Boilers , Stress , Flow (Dynamics) , Cooling , Heat transfer , Mechanical behavior , Modeling , Oscillations , Risk , Safety

Sloshing Characteristics of Single Deck Floating Roofs in Aboveground Storage Tanks: Natural Periods and Vibration Modes

Shoichi Yoshida, Kazuyoshi Sekine, Katsuki Iwata

PVP 2009; 191-199doi:https://doi.org/10.1115/PVP2009-77187

Abstract

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Topics: Roofs , Sloshing , Storage tanks , Vibration , Fluids , Damage , Design , Earthquakes , Engineers , Evaporation

Buckling Characteristics of Floating Roof Pontoons in Aboveground Storage Tanks Subjected to Both Compressive and Bending Load

Shoichi Yoshida

PVP 2009; 201-210doi:https://doi.org/10.1115/PVP2009-77227

Abstract

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Topics: Buckling , Roofs , Storage tanks , Stress , Failure , Sloshing , Bifurcation , Buoyancy , Damage , Earthquakes

Improvements of the Containment Measuring System

Jiri Zdarek, Jan Bulak, Petr Vomacka, Milan Brumovsky

PVP 2009; 211-215doi:https://doi.org/10.1115/PVP2009-77400

Abstract

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Topics: Containment , Stress , Tendons , Nuclear power stations , Computation , Concretes , Emergencies , Expert systems , In-service inspection , Modeling

PTS Evaluation for Czech Nuclear Power Plants of WWER Type

Vladislav Pistora, Pavel Kral

PVP 2009; 217-224doi:https://doi.org/10.1115/PVP2009-77405

Abstract

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Topics: Nuclear power stations , Finite element methods , Fracture (Materials) , Stress , Emergency core cooling systems , Temperature , Brittleness , Circuits , Computation , Computers

Cracking in Welds of Heavy-Wall Stainless Steel and Nickel Alloy Piping During Fabrication

Tomoaki Kiso, Kunio Ishii, Ichiro Seshimo

PVP 2009; 225-232doi:https://doi.org/10.1115/PVP2009-77554

Abstract

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Topics: Cracking (Materials) , Fracture (Process) , Manufacturing , Nickel alloys , Pipes , Stainless steel , Welded joints , Heat treating (Metalworking) , Stress , Alloys

Experiences With Controlled Deposition Welding and Fitness for Service in Coke Drums

Jorge A. Penso, M. Victor Li

PVP 2009; 233-241doi:https://doi.org/10.1115/PVP2009-77853

Abstract

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Topics: Coke , Fitness-for-service , Welding , Charge density waves , Maintenance , Base metals , Computer simulation , Fatigue , Heat , Heat treating (Metalworking)

Effects of Cladding on Reactor Pressure Vessel Integrity Based on the Revised PTS Rule (10 CFR 50.61)

Vikram Marthandam, Timothy J. Griesbach, Jack Spanner

PVP 2009; 243-249doi:https://doi.org/10.1115/PVP2009-78088

Abstract

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Topics: Cladding systems (Building) , Reactor vessels , Density , Nondestructive evaluation , ASME Standards , Cracking (Materials) , Fracture (Process) , Inspection , Thermal shock , Transients (Dynamics)

Piping and Supports

Transient Flow Analysis of Spring Loaded Pressure Safety Valve

Xue Guan Song, Seong Gul Kim, Lin Wang, Young Chul Park

PVP 2009; 253-258doi:https://doi.org/10.1115/PVP2009-77043

Abstract

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Topics: Pressure , Safety , Springs , Unsteady flow , Valves , Disks , Computational fluid dynamics , Fluids , Geometry , Design

Buckling Analysis of Plastic Pipe Reinforced by Cross-Winding Steel Wire Under Bending

Xiang Li, Jinyang Zheng, Fengjian Shi, Yongquan Qin, Ping Xu

PVP 2009; 259-268doi:https://doi.org/10.1115/PVP2009-77532

Abstract

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Topics: Buckling , Composite materials , Finite element analysis , Plastic pipes , Steel , Winding (process) , Wire

Experimental Measurement of the Permeability of Die-Formed Exfoliated Graphite Compression Packings

Didier Lasseux, Pascal Jolly, Yves Jannot, Emmanuel Sauger, Benoit Omnes

PVP 2009; 269-278doi:https://doi.org/10.1115/PVP2009-77659

Abstract

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Topics: Compression , Graphite , Packings (Cushioning) , Permeability , Pressure , Anisotropy , Gas flow , Leakage , Manufacturing , Nitrogen

Method for Predicting Mixing Tee Thermal Fatigue in Carbon Steel Based on Austenitic Stainless Steel Operating Experience

Robert O. McGill, David O. Harris, Ken Wolfe

PVP 2009; 279-286doi:https://doi.org/10.1115/PVP2009-77975

Abstract

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Topics: Carbon steel , Fatigue , Stainless steel , Leakage , Pipes , Boiling water reactors , Fatigue cracks , Fluids , Heat , Piping systems

GRE Pipeline Installation Procedures: A Field Case Study

A. Khalaf, Y. Al-Tartoor, A. C. Seibi, A. Karrech

PVP 2009; 287-295doi:https://doi.org/10.1115/PVP2009-78017

Abstract

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Topics: Pipelines , Pipes , Failure , Pipe sizes , Stress , Cantilever beams , Deflection , Deformation , Epoxy adhesives , Epoxy resins

Aging Management and Life Extension

Reporting on Plant Condition: The Big Picture

Quentin D. Gryl, Robert H. Frith

PVP 2009; 299-309doi:https://doi.org/10.1115/PVP2009-77012

Abstract

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Topics: Design , Hazards , Industrial plants , Maintenance , Performance

Managing Change in a High Growth Environment: Reference to Bahrain/Arabian Gulf

Aby Thomas

PVP 2009; 311-321doi:https://doi.org/10.1115/PVP2009-77036

Abstract

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Topics: American Petroleum Institute , Construction , Gas industry , Natural gas fields , Petroleum , Piping systems , Safety

A Generalization of the FAVOR Code to Include BWR Geometries and Heat-Up Transients

Terry Dickson, Shengjun Yin, Paul Williams

PVP 2009; 323-331doi:https://doi.org/10.1115/PVP2009-77106

Abstract

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Topics: Boiling water reactors , Heat , Transients (Dynamics) , Pressurized water reactors , Fracture mechanics , Computers , Radiation (Physics) , Stress , Tension , Embrittlement

The Sensitivity of Risk-Informed Reactor Structural Integrity Analysis Results to Various Interpretations of Warm Pre-Stress

Mark T. EricksonKirk, Terry L. Dickson

PVP 2009; 333-339doi:https://doi.org/10.1115/PVP2009-77127

Abstract

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Topics: Risk , Stress , Transients (Dynamics) , Fracture (Materials) , Fracture (Process) , Accidents , Failure , Modeling , Temperature , Vessels

Preparation of Long Term Operation in Dukovany NPP, Czech Republic

Robert Krivanek

PVP 2009; 341-346doi:https://doi.org/10.1115/PVP2009-77231

Abstract

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Topics: Nuclear power stations , Risk analysis , Design , Safety

Implementation of PLIM and AMPs in Czech NPPs

Robert Krivanek

PVP 2009; 347-353doi:https://doi.org/10.1115/PVP2009-77233

Abstract

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Topics: Amperes , Nuclear power stations , Power stations

Nuclear PWR Plants Mitigation of Reactor Coolant System Areas to Consider Plants Aging Management and/or Life Extension

Re´mi Thevenet

PVP 2009; 355-374doi:https://doi.org/10.1115/PVP2009-77354

Abstract

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Topics: Life extension , Nuclear reactor coolants , Pressurized water reactors , Fracture (Materials) , Risk , Water , Maintenance , Nozzles , Reactor vessels , Alloys

Remaining Lifetime Evaluation of High Temperature Components of Power Plant Steam Boilers: Case Studies

Vaclav Mentl, Va´clav Lisˇka, Jaroslav Koc, Michal Chocholousˇek

PVP 2009; 375-381doi:https://doi.org/10.1115/PVP2009-77381

Abstract

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Topics: Boilers , High temperature , Power stations , Safety , Stress , Temperature , Inspection , Creep , Failure , Fatigue

CFD-Tools for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Thermal-Hydraulic Methods and Main Industrial Results on the French 900 MWe PWR RPV

A. Martin, F. Lestang, S. Bellet, D. Guichard, C. Vit, S. Cornille, A. Barbier, F. Huvelin

PVP 2009; 383-391doi:https://doi.org/10.1115/PVP2009-77390

Abstract

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Topics: Computational fluid dynamics , Fracture mechanics , Pressure , Pressurized water reactors , Reactor vessels , Thermal shock

Development of Component Specific Ageing Management Programmes for Mechanical Components at the NPP Paks

A´gnes Ja´nosine´ Bi´ro´, Sa´ndor Ra´tkai, Ma´rton Osztheimer, Katalin Baumann-ne´ Tanits, Sa´ndor Baranya

PVP 2009; 393-402doi:https://doi.org/10.1115/PVP2009-77504

Abstract

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Topics: Acceptance criteria , Boilers , Coolants , Corrective actions , Corrosion , Damage , Emergencies , Emergency core cooling systems , Erosion , Fasteners

ARCMAC Optical Strain Measurement for Creep Monitoring: Recent Improvements in Accuracy and Resolution

Andy Morris, Iain Palmer, Chris Maharaj, Amit Puri, John Dear

PVP 2009; 403-410doi:https://doi.org/10.1115/PVP2009-77511

Abstract

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Topics: Creep , Resolution (Optics) , Strain measurement , Pipes , Steam , Errors , Gages , Strain gages , Blades , Design

Extension of Operational Life-Time of WWER-440/213 Type Units at Paks Nuclear Power Plant

Tama´s Ja´nos Katona, Sa´ndor Ra´tkai, A´gnes Ja´nosine´ Bi´ro´

PVP 2009; 411-418doi:https://doi.org/10.1115/PVP2009-77513

Abstract

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Topics: Nuclear power stations , Design , Licensing , Safety , Engineering systems and industry applications , Thermal energy

Degradation Mechanisms Control of Mechanical Components During Operation

Lubomir Junek, Jaroslav Bartonicek, Milan Vrana

PVP 2009; 419-425doi:https://doi.org/10.1115/PVP2009-77655

Abstract

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Topics: Corrosion , Damage , Design , Dimensions , Dynamic testing (Materials) , Emergencies , Errors , Failure , Geometry , Inspection

Microstructure and Mechanical Properties of G17CrMoV5 – 10 Cast Steel After Regenerative Heat Treatment

Grzegorz Golan´ski

PVP 2009; 427-434doi:https://doi.org/10.1115/PVP2009-77710

Abstract

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Topics: Heat treating (Metalworking) , Mechanical properties , Steel , Temperature , Brittleness , Steam turbines , Tensile strength , Yield strength

Integrity and Life Assessment of Cast Duplex Stainless Steel Elbows Used in the Primary Loops of PWRs

N. Ligneau, C. Page`s, M. Akamatsu, C. Pokor, V. Calonne-Chatelee

PVP 2009; 435-443doi:https://doi.org/10.1115/PVP2009-77731

Abstract

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Topics: Pressurized water reactors , Stainless steel , Fracture toughness , Manufacturing , Casting , Cavities , Crack propagation , Databases , Embrittlement , Engineering instruments

Statical Computation of the Main Building

Istva´n Mo´ga

PVP 2009; 445-452doi:https://doi.org/10.1115/PVP2009-77735

Abstract

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Topics: Computation , Regulations

Assessment of the Fatigue Life of a PWR Surge Line Including the Effect of Coolant Environment

Gu¨nter Ko¨nig, Jaroslav Bartonicek, Horst Rothenho¨fer

PVP 2009; 453-460doi:https://doi.org/10.1115/PVP2009-77739

Abstract

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Topics: Coolants , Fatigue life , Pressurized water reactors , Surges , Design , Failure , Fatigue , Boundary-value problems , Corrosion , Damage

Materials Aging Degradation of Reactor Vessel Internals: Part III—Structural Evaluation and Local Finite Element Models

Matthew D. Snyder, Tama´s R. Liszkai, Anne Demma

PVP 2009; 461-468doi:https://doi.org/10.1115/PVP2009-77784

Abstract

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Topics: Finite element model , Reactor vessels , Manufacturing , Computational fluid dynamics , Constitutive equations , Failure mechanisms , Pressurized water reactors , Radiation (Physics) , Stress , Structural analysis

Materials Aging Degradation of Reactor Vessel Internals: Part II—Structural Evaluation and Global Finite Element Models

Tama´s R. Liszkai, Matthew Snyder, Anne Demma

PVP 2009; 469-479doi:https://doi.org/10.1115/PVP2009-77786

Abstract

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Topics: Finite element model , Reactor vessels , Manufacturing , Computational fluid dynamics , Pressurized water reactors , Constitutive equations , Failure mechanisms , Radiation (Physics) , Stress , Structural analysis

On the Role of Fracture Mechanics Assessment Within the Integrity Concept

Guenter Koenig, Jaroslav Bartonicek, Friedrich Schoeckle

PVP 2009; 481-488doi:https://doi.org/10.1115/PVP2009-77889

Abstract

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Topics: Fracture mechanics , Fracture (Materials) , Stress , Damage , Design , Leakage , Manufacturing , Safety , Collapse , Construction

VVER-440 NPP Reactor Vessel and Reactor Internals Design Review Calculation Using ASME BPVC

Tama´s Pa´lfi, Pe´ter Pa´lfi, Sa´ndor Ra´tkai, Sa´ndor Dancso´

PVP 2009; 489-493doi:https://doi.org/10.1115/PVP2009-77908

Abstract

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Topics: ASME Boiler and Pressure Vessel Code , Design , Nuclear power stations , Reactor vessels , Structural analysis , ASME Standards , Computation , Cycles , Fatigue , Gates (Closures)

Detected Flaw Evaluation on VVER Reactor Components Using ASME Code

Tama´s Pa´lfi, Sa´ndor Ra´tkai

PVP 2009; 495-499doi:https://doi.org/10.1115/PVP2009-77909

Abstract

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Topics: ASME Standards , Fracture (Materials) , Defect analysis , Finite element analysis , Materials properties , Shapes , Welded joints

Design Review of the VVER-440 NPP Main Components on the Base of ASME BPVC

Ja´nos Boros, Tama´s Pa´lfi, Pe´ter Pa´lfi, Sa´ndor Ra´tkai

PVP 2009; 501-507doi:https://doi.org/10.1115/PVP2009-77910

Abstract

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Topics: ASME Boiler and Pressure Vessel Code , Design , Nuclear power stations , ASME Standards

Assessment and Management of Ageing of Civil Structures of Paks NPP

Tama´s Katona, Sa´ndor Ra´tkai, Pe´ter Go˝si, Istva´n Mo´ga

PVP 2009; 509-520doi:https://doi.org/10.1115/PVP2009-77911

Abstract

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Topics: Nuclear power stations , Structures , Concretes , Structural elements (Construction) , Carbon steel , Coating processes , Coatings , Concrete cracking , Corrosion , Licensing

Adaptation of BPVC Section XI Requirements: The Operator’s and the Regulator’s Perspective

P. Babics, S. Ratkai, D. Szabo, P. Trampus

PVP 2009; 521-528doi:https://doi.org/10.1115/PVP2009-77920

Abstract

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Topics: ASME Boiler and Pressure Vessel Code , ASME Standards , Construction , Design , Inspection , Licensing , Maintenance , Nuclear power stations , Safety

New Safety Assessment System for Corroded Underground Pipelines

Szabolcs Sza´vai, Gyo¨ngyve´r B. Lenkey

PVP 2009; 529-536doi:https://doi.org/10.1115/PVP2009-77959

Abstract

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Topics: Safety , Underground pipelines , Failure , Pipelines , Pipes , Corrosion , Finite element analysis , Finite element methods , Finite element model , Metals

New PLIM Program for Czech NPPs

Petr Kadecˇka

PVP 2009; 537-544doi:https://doi.org/10.1115/PVP2009-77980

Abstract

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Topics: Nuclear power stations , Databases , Design , Nuclear research

An Overview of the Research by EC-JRC/IE on Enhancement of Maintenance Efficiency of Nuclear Power Plants

Paolo Contri, Irina Kuzmina

PVP 2009; 545-552doi:https://doi.org/10.1115/PVP2009-78060

Abstract

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Topics: Maintenance , Nuclear power stations , Optimization , Public utilities

The Effect of Post-Irradiation Annealing on VVER-440 RPV Materials Mechanolocal Properties and Nano-Structure Under Re-Irradiation

S. Rogozkin, A. Chernobaeva, A. Aleev, A. Nikitin, A. Zaluzhnyi, D. Erak, Ya. Shtrombakh, O. Zabusov, L. Debarberis, A. Zeman

PVP 2009; 553-562doi:https://doi.org/10.1115/PVP2009-78128

Abstract

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Topics: Annealing , Irradiation (Radiation exposure) , Nanostructures , Embrittlement , Atoms , Nuclear power stations , Phase transition temperature , Probes , Surveillance

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