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Proceedings Papers

Pressurized Thermal Shock Analysis With Sub-Modeling

L. Stefanini, C. Versteylen, F. S. L. Pangukir, H. J. Uitslag-Doolaard, F. H. E. de Haan - de Wilde
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T05A014, July 13–15, 2021
Paper No: PVP2021-61794
DOI: https://doi.org/10.1115/PVP2021-61794
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Topics: Computational fluid dynamics, Modeling, Thermal shock
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

Fatigue Failure Predictions Based on FEA Fracture Mechanics Simulations

F. H. E. de Haan - de Wilde, M. H. C. Hannink, F. J. Blom
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A111, August 3, 2020
Paper No: PVP2020-21846
DOI: https://doi.org/10.1115/PVP2020-21846
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Topics: Engineering simulation, Fatigue failure, Fatigue life, Finite element analysis, Fracture (Materials), Fracture mechanics, Nozzles, Simulation
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

High Flux Reactor Continued Safe Operation: Time Limited Ageing Analyses

L. Stefanini, F. H. E. de Haan - de Wilde
Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A010, August 3, 2020
Paper No: PVP2020-21032
DOI: https://doi.org/10.1115/PVP2020-21032
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Topics: Biomedicine, Equipment qualification, Fatigue, Irradiation (Radiation exposure), Isotopes, Leak-before-break, Manufacturing, Nuclear reactors, Reactor vessels
Proceedings Papers

An Update on the Investigation of Fracture Toughness Properties of the High Flux Reactor Vessel From Surveillance Test Campaign in 2017

M. Kolluri, F. H. E. de Haan – de Wilde, H. S. Nolles, A. J. M. de Jong
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A008, July 14–19, 2019
Paper No: PVP2019-93043
DOI: https://doi.org/10.1115/PVP2019-93043
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Topics: Fracture toughness, Reactor vessels, Surveillance, Fracture (Materials), Fluence (Radiation measurement), Neutrons, Vessels, Mechanical properties, Alloys, Damage
Proceedings Papers

International Civil Ageing Management and Assessment Methodology of Concrete

F. H. E. de Haan – de Wilde, C. G. M. de Bont
Proc. ASME. PVP2019, Volume 7: Operations, Applications, and Components, V007T07A008, July 14–19, 2019
Paper No: PVP2019-93029
DOI: https://doi.org/10.1115/PVP2019-93029
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Topics: Concretes, Modeling, Nuclear power stations, Amperes, Engineering standards, Finite element analysis, Industrial research, Pipes, Vessels
Proceedings Papers

Continued Safe Operation (LTO Research Reactors) High Flux Reactor, Petten

L. Stefanini, F. H. E. de Haan – de Wilde, J. F. Offerein
Proc. ASME. PVP2019, Volume 7: Operations, Applications, and Components, V007T07A009, July 14–19, 2019
Paper No: PVP2019-93030
DOI: https://doi.org/10.1115/PVP2019-93030
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Topics: Biomedicine, Engineering standards, Isotopes, Safety
Proceedings Papers

Overview of International Implementation of Environmental Fatigue (Update)

F. H. E. de Haan-de Wilde, F. J. Blom
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A015, July 16–20, 2017
Paper No: PVP2017-65006
DOI: https://doi.org/10.1115/PVP2017-65006
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Topics: Fatigue, Nuclear power stations, Water, Coolants, Fatigue life, Testing
Proceedings Papers

Irradiation Induced Changes in Mechanical and Microstructural Properties of the High Flux Reactor Vessel: Update of the Results From 2014 and 2015 Surveillance Test Campaigns

M. Kolluri, F. H. E. de Haan-de Wilde, H. S. Nolles, A. J. M. de Jong, F. A. van den Berg
Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A018, July 16–20, 2017
Paper No: PVP2017-65007
DOI: https://doi.org/10.1115/PVP2017-65007
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Topics: Irradiation (Radiation exposure), Reactor vessels, Surveillance, Vessels, Neutrons, Damage, Fluence (Radiation measurement), Mechanical properties, Alloys, Fracture toughness
Proceedings Papers

Quantitative Comparison of Environmental Fatigue Methods

F. H. E. de Haan - de Wilde, F. J. Blom, M. H. C. Hannink
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A027, July 19–23, 2015
Paper No: PVP2015-45027
DOI: https://doi.org/10.1115/PVP2015-45027
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Topics: Fatigue, Alloys, Nickel alloys, Steel, Carbon steel, Carbon, Nozzles, Nuclear power stations, Plasma spraying, Spraying (Coating processes)
Proceedings Papers

Overview of International Implementation of Environmental Fatigue

F. H. E. de Haan - de Wilde, M. H. C. Hannink, F. J. Blom
Proc. ASME. PVP2013, Volume 1A: Codes and Standards, V01AT01A025, July 14–18, 2013
Paper No: PVP2013-97695
DOI: https://doi.org/10.1115/PVP2013-97695
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Topics: Fatigue, Nuclear power stations, Water, Coolants, Testing