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Proceedings Papers

Experimental Investigation of Jet Cross-Flow Induced Vibration of a Rod Bundle

Ibrahim Gad-el-Hak, Njuki Mureithi, Kostas Karazis, Gary Williams
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A014, July 13–15, 2021
Paper No: PVP2021-65000
DOI: https://doi.org/10.1115/PVP2021-65000
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Topics: Accidents, Coolants, Cross-flow, Fuel rods, Jets, Pressurized water reactors, Vibration
Proceedings Papers

Application of Leak-Before-Break to Small Diameter Stainless Steel Piping in PWRs

Nathaniel G. Cofie, Dilip Dedhia, Do Jun Shim
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A038, July 13–15, 2021
Paper No: PVP2021-62368
DOI: https://doi.org/10.1115/PVP2021-62368
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Topics: Leakage, Leak-before-break, Pipes, Pressurized water reactors, Stainless steel
Proceedings Papers

Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels

Frideriki Naziris, Casper Versteylen, Frederick Frith, Marcel Bregman, Murthy Kolluri
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A064, July 13–15, 2021
Paper No: PVP2021-61027
DOI: https://doi.org/10.1115/PVP2021-61027
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Topics: Irradiation (Radiation exposure), Manufacturing, Reactor vessels, Steel, Tension, Testing, Geometry, Stress, ASTM International, Pressurized water reactors
Proceedings Papers

European Project ATLAS+: Large Scale Fracture Mechanics Tests on Ferritic Pipes

Anna Dahl, Willy Vincent
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A028, July 13–15, 2021
Paper No: PVP2021-61834
DOI: https://doi.org/10.1115/PVP2021-61834
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Topics: Fracture mechanics, Pipes, Steel, Fracture (Materials), Design, Feedwater, Pressurized water reactors, Shapes, Stainless steel, Temperature
Proceedings Papers

30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly

Elena Kalinina, Doug Ammerman, Carissa Grey, Gregg Flores, Lucas Lujan, Sylvia Saltzstein, Danielle Michel
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A022, July 13–15, 2021
Paper No: PVP2021-60533
DOI: https://doi.org/10.1115/PVP2021-60533
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Topics: Cladding systems (Building), Fuels, Manufacturing, Pressure, Pressurized water reactors, Spent nuclear fuels, Stress-strain curves, Arches, Bending (Stress), Blanks
Proceedings Papers

An Update of the Assessment Methodology for Civil Ageing Management for LTO/CSO Based on International Standards and Engineering Judgement

F. H. E. de Haan - de Wilde, M. J. Janssen
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A008, July 13–15, 2021
Paper No: PVP2021-61499
DOI: https://doi.org/10.1115/PVP2021-61499
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Topics: Amperes, Concretes, Containment, Engineering standards, Finite element analysis, Maintenance, Modeling, Nuclear power stations, Nuclear reactors, Performance
Proceedings Papers

Design by Analysis, Codes, Standards and Rules on EAF - Applicability to Stainless Steels in PWR Primary Piping

Jussi Solin, Tommi Seppänen, Rami Vanninen, Erkki Pulkkinen, Petri Lemettinen
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A011, July 13–15, 2021
Paper No: PVP2021-62187
DOI: https://doi.org/10.1115/PVP2021-62187
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Topics: Design, Electric arc furnaces, Fatigue, Pipes, Pressurized water reactors, Stainless steel, ASME Boiler and Pressure Vessel Code, Engineering standards, Fatigue analysis, Life cycle management
Proceedings Papers

Technical Basis for Increased Inspection Interval of Cold Leg Pressurized Water Reactor Dissimilar Metal Welds Using xLPR

Chris Lohse, Do Jun Shim, Dilip Dedhia, Rohan Dutta, Nathan Glunt
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A030, July 13–15, 2021
Paper No: PVP2021-62560
DOI: https://doi.org/10.1115/PVP2021-62560
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Topics: Inspection, Metals, Pressurized water reactors, Welded joints, Fracture (Materials), Alloys, ASME Standards, Computers, Probability, Temperature
Proceedings Papers

A Method for Investigating Multi-Axial Fatigue in a PWR Environment

Peter Gill, Paul Onwuarolu, Russell Smith, Ben Coult, Mark Kirkham, Matt Sutcliffe, Karen Cooper, Tom Schofield, Colin Madew, Alec McLennan, Chris Currie
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A012, July 13–15, 2021
Paper No: PVP2021-62429
DOI: https://doi.org/10.1115/PVP2021-62429
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Topics: Fatigue, Pressurized water reactors, Stress, Fatigue testing, Cycles, Failure, Finite element analysis, Cracking (Materials), Fracture (Process), Design
Proceedings Papers

Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels

Adam Griffiths, Peter Gill, Ben Coult, Jack Beswick, Norman Platts, Jonathan Mann, Chris Currie, Joe Airey
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A013, July 13–15, 2021
Paper No: PVP2021-62909
DOI: https://doi.org/10.1115/PVP2021-62909
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Topics: Fatigue, Fracture (Materials), Stainless steel, Testing, Grain size, Heat, Nucleation (Physics), Stress, Analytical methods, ASME Standards
Proceedings Papers

Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments

Russell C. Cipolla, Warren H. Bamford, Kiminobu Hojo, Yuichiro Nomura
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A001, July 13–15, 2021
Paper No: PVP2021-61728
DOI: https://doi.org/10.1115/PVP2021-61728
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Topics: Fatigue cracks, Pressurized water reactors, Stainless steel
Proceedings Papers

A Fatigue Crack Growth Model for Type 304 Austenitic Stainless Steels In a Pressurized Water Reactor Environment

Kathleen C. Barron, Denise J. Paraventi
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A015, July 13–15, 2021
Paper No: PVP2021-65973
DOI: https://doi.org/10.1115/PVP2021-65973
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Topics: Fatigue cracks, Pressurized water reactors, Stainless steel
Proceedings Papers

Comparison of International Codes for a Fatigue Crack Growth Flaw Tolerance Sample Problem

Gary L. Stevens
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A008, July 13–15, 2021
Paper No: PVP2021-61651
DOI: https://doi.org/10.1115/PVP2021-61651
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Topics: Fatigue cracks, ASME Standards, Pressurized water reactors, Coolants, Electricity (Physics), Engineering standards, Fatigue, Japan Society of Mechanical Engineers, JSME Standards, Pipes
Proceedings Papers

Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking

Stephen Marlette, Steven L. McCraken, Christopher Lohse
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A097, August 3, 2020
Paper No: PVP2020-21544
DOI: https://doi.org/10.1115/PVP2020-21544
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Topics: Fatigue cracks, Maintenance, Pipes, Stainless steel, Overlays (Materials engineering), Fatigue, Boiling water reactors, Pressurized water reactors, Stress corrosion cracking, Design
Proceedings Papers

Probabilistic Leak Before Break Using the R6 Methodology

Peter Gill
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A110, August 3, 2020
Paper No: PVP2020-21769
DOI: https://doi.org/10.1115/PVP2020-21769
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Topics: Leak-before-break, Stress, Computer software, Failure, Probability, Reliability, Fracture (Materials), Fracture mechanics, Inspection, Leakage
Proceedings Papers

Comparative Evaluation of Plastic Design Methods for Fatigue Assessment of a Nuclear Class 1 Piping Nozzle

David M. Clarkson, Christopher D. Bell, Donald Mackenzie
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A043, August 3, 2020
Paper No: PVP2020-21271
DOI: https://doi.org/10.1115/PVP2020-21271
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Topics: Design methodology, Fatigue, Nozzles, Pipes, Design, Finite element analysis, ASME Boiler and Pressure Vessel Code, Pressurized water reactors, Stress, Coolants
Proceedings Papers

An Assessment Methodology for Civil Ageing Management and Concrete for LTO/CSO Based on International Standards and Engineering Judgement

F. H. E. de Haan - de Wilde, C. G. M. de Bont
Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A013, August 3, 2020
Paper No: PVP2020-21838
DOI: https://doi.org/10.1115/PVP2020-21838
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Topics: Amperes, Concretes, Engineering standards, Containment, Pressurized water reactors, Steel, Finite element analysis, Maintenance, Modeling, Nuclear power stations
Proceedings Papers

Crack Propagation Modeling in a PWR Under PTS Using XFEM

Diego F. Mora, Markus Niffenegger, Roman Mukin
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A001, August 3, 2020
Paper No: PVP2020-21026
DOI: https://doi.org/10.1115/PVP2020-21026
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Topics: Crack propagation, Modeling, Pressurized water reactors, Fracture (Materials), Damage, Finite element analysis, Fracture toughness, Accidents, Cooling, Simulation
Proceedings Papers

European Project ATLAS+: Status of the WP1 Relative to the Experimental Program on Pipes and Specimens

Dominique Moinereau, Tomas Nicak, Anna Dahl
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A048, August 3, 2020
Paper No: PVP2020-21844
DOI: https://doi.org/10.1115/PVP2020-21844
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Topics: Pipes, Fracture (Materials), Fracture (Process), Stainless steel, Alloys, Feedwater, Materials properties, Pressurized water reactors, Steel
Proceedings Papers

Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs

Maksym Zarazovskii, Volodymyr Revka, Liudmyla Chyrko
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A018, August 3, 2020
Paper No: PVP2020-21748
DOI: https://doi.org/10.1115/PVP2020-21748
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Topics: Brittleness, Databases, Embrittlement, Phase transition temperature, Radiation (Physics), Regression analysis, Surveillance, Temperature, Welded joints, Silicon