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Proceedings Papers

Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor

Henry Cathcart, James Finley, John Taylor, Alexander Frost
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A055, July 17–22, 2022
Paper No: PVP2022-84742
DOI: https://doi.org/10.1115/PVP2022-84742
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Topics: Atoms, Bricks, Carbon, Dimensions, Emissions, Failure, Failure analysis, Finite element analysis, Fluence (Radiation measurement), Fuels
Proceedings Papers

Coupling of Neutron Transport and Probabilistic Fracture Mechanics Codes for Analysis of Embrittled Reactor Pressure Vessels

Benjamin W. Spencer, William M. Hoffman, Benjamin S. Collins, Shane C. Henderson
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A057, August 3, 2020
Paper No: PVP2020-21680
DOI: https://doi.org/10.1115/PVP2020-21680
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Topics: Embrittlement, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Reactor vessels
Proceedings Papers

Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

Preeti Doddihal, Dennis Kawa, Douglas Scarth, Yu Chen
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A013, July 14–19, 2019
Paper No: PVP2019-93671
DOI: https://doi.org/10.1115/PVP2019-93671
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Topics: Annulus, Finite element analysis, Nuclear reactors, Fracture (Materials), Fracture (Process), Strips, Fuels, Irradiation (Radiation exposure), Pressure, Stress
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Chinese RPV Steels

Yupeng Cao, Yinbiao He, Binxi Wang, Yifeng Huang, Hui Li, Yan Yu, Hu Hui
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A028, July 14–19, 2019
Paper No: PVP2019-93615
DOI: https://doi.org/10.1115/PVP2019-93615
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Topics: Embrittlement, Irradiation (Radiation exposure), Steel, Forging, China, Fluence (Radiation measurement), Fracture toughness, Mechanical properties, Notch testing, Nuclear power stations
Proceedings Papers

Assessment of Structural Integrity on Irradiated Steel Structure: Focusing on Long Column Type Reactor Pressure Vessel Supports

Goeun Han, Sukru Guzey
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A020, July 14–19, 2019
Paper No: PVP2019-93640
DOI: https://doi.org/10.1115/PVP2019-93640
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Topics: Reactor vessels, Steel, Fitness-for-service, Neutrons, Irradiation (Radiation exposure), American Petroleum Institute, Coolants, Finite element model, Fluence (Radiation measurement), Fracture toughness
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

Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4

Kai Lu, Jinya Katsuyama, Yinsheng Li, Shinobu Yoshimura
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A057, July 14–19, 2019
Paper No: PVP2019-93935
DOI: https://doi.org/10.1115/PVP2019-93935
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Topics: Fracture mechanics, Reactor vessels, Failure, Neutrons, Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Light water reactors, Nondestructive evaluation, Nuclear power
Proceedings Papers

PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution

Masato Yamamoto, Masaki Nagai
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A037, July 14–19, 2019
Paper No: PVP2019-93964
DOI: https://doi.org/10.1115/PVP2019-93964
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Topics: Fracture toughness, Base metals, Fracture (Materials), Belts, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Nuclear research, Probability, Surveillance
Proceedings Papers

Evaluation of Through Wall Fracture Toughness Distribution of IAEA Reference Material JRQ by Mini-C(T) Specimens and the Master Curve Method

Masato Yamamoto, Tomohiro Kobayashi
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A071, July 15–20, 2018
Paper No: PVP2018-84889
DOI: https://doi.org/10.1115/PVP2018-84889
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Topics: Fracture toughness, Temperature, Fluence (Radiation measurement), Fracture (Materials), Reactor vessels, Regulations, Stress, Thermal shock, Wall thickness
Proceedings Papers

Presentation of DEFI-PROSAFE Project: Probabilistic Methodology to Assess Margin in Deterministic RPV Integrity Assessment and Proposed Benchmark

Ralf Tiete, Richard Trewin, Sebastien Blasset, Vladislav Pistora, Miroslav Posta, Markus Niffenegger, Guian Qian
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A074, July 15–20, 2018
Paper No: PVP2018-84615
DOI: https://doi.org/10.1115/PVP2018-84615
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Topics: Accounting, Failure, Fluence (Radiation measurement), Fracture (Materials), Fracture (Process), Neutrons, Nozzles, Probability, Reactor vessels, Risk
Proceedings Papers

Effect of Uncontrolled Hydrogen Injection on SCC Susceptibility of 304L Steel in High Temperature Water

A. L. Medina-Almazán, G. Galicia-Aguilar, J. C. Zenteno-Suárez, C. Arganis-Juárez, N. López-García, M. Marín-Almazo
Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A032, July 16–20, 2017
Paper No: PVP2017-65040
DOI: https://doi.org/10.1115/PVP2017-65040
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Topics: High temperature, Hydrogen, Steel, Water, Boiling water reactors, Brittleness, Corrosion, Fatigue cracks, Light water reactors, Nuclear power stations
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

The EPRI PWR Supplemental Surveillance Program (PSSP) Final Design and Implementation

William Server, Brian Burgos, Tim Hardin, J. Brian Hall
Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A021, July 16–20, 2017
Paper No: PVP2017-65307
DOI: https://doi.org/10.1115/PVP2017-65307
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Topics: Design, Pressurized water reactors, Surveillance, Electricity (Physics), Fluence (Radiation measurement), Fracture toughness, Irradiation (Radiation exposure), Neutrons, Phase transition temperature, Reactor vessels
Proceedings Papers

Probabilistic Fracture Mechanics Analysis of Boiling Water Reactor Vessel on Relatively Low Failure Probability Problem Using PROFAS-RV PFM Analysis Code

Jongmin Kim, Bongsang Lee
Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A001, July 16–20, 2017
Paper No: PVP2017-65225
DOI: https://doi.org/10.1115/PVP2017-65225
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Topics: Boiling water reactors, Failure, Fracture mechanics, Probability, Vessels, Fluence (Radiation measurement), Transients (Dynamics), Irradiation (Radiation exposure), Reactor vessels, Stress
Proceedings Papers

Current Status of the Characterization of RPV Materials Harvested From the Decommissioned Zion Unit 1 Nuclear Power Plant

Thomas M. Rosseel, Mikhail A. Sokolov, Xiang Chen, Randy K. Nanstad
Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A059, July 16–20, 2017
Paper No: PVP2017-65090
DOI: https://doi.org/10.1115/PVP2017-65090
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Topics: Nuclear power stations, Base metals, Light water reactors, Mechanical properties, Atoms, Cutting, Embrittlement, Fluence (Radiation measurement), Fracture toughness, Heat
Proceedings Papers

Application of Master Curve Approach to Surveillance Test Data for WWER-1000 Reactor Pressure Vessels

Volodymyr M. Revka, Liudmyla I. Chyrko
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A066, July 16–20, 2017
Paper No: PVP2017-65518
DOI: https://doi.org/10.1115/PVP2017-65518
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Topics: Reactor vessels, Surveillance, Fracture toughness, Metals, Electromagnetic scattering, Irradiation (Radiation exposure), Temperature, Embrittlement, Neutrons, Radiation (Physics)
Proceedings Papers

Upper Shelf Energy Prediction Model for Irradiated Reactor Vessel Steels

Takuya Ogawa, J. Brian Hall, Benjamin E. Mays, Timothy C. Hardin
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A009, July 16–20, 2017
Paper No: PVP2017-65317
DOI: https://doi.org/10.1115/PVP2017-65317
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Topics: Reactor vessels, Steel, ASTM International, Databases, Copper, Embrittlement, Irradiation (Radiation exposure), Light water reactors, Surveillance, Chemistry
Proceedings Papers

Swelling of VVER-1000 Core Baffle: Numerical Modeling and Direct Measurement of its Geometrical Dimensions

Andrii Oryniak, Igor Orynyak
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A019, July 16–20, 2017
Paper No: PVP2017-65769
DOI: https://doi.org/10.1115/PVP2017-65769
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Topics: Computer simulation, Dimensions, Gages, Geometry, Nuclear power stations, Stress, Accounting, Boundary-value problems, Brittleness, Coolants
Proceedings Papers

The Master Curve Fracture Toughness Evaluation of Irradiated Plate Material JRQ Using Miniature-C(T) Specimens

Masato Yamamoto
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A071, July 16–20, 2017
Paper No: PVP2017-66085
DOI: https://doi.org/10.1115/PVP2017-66085
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Topics: Fracture toughness, Steel, Base metals, Cracking (Materials), Dimensions, Fluence (Radiation measurement), Fracture (Process), Machining, Neutrons, Reactor vessels
Proceedings Papers

Embrittlement Trend Curves for Notch and Fracture Toughness of 15Kh2MFAA Type Steel

Milan Brumovsky, Radim Kopřiva, Miloš Kytka
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A063, July 16–20, 2017
Paper No: PVP2017-65174
DOI: https://doi.org/10.1115/PVP2017-65174
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Topics: Embrittlement, Fracture toughness, Steel, Surveillance, Reactor vessels, Databases, Fluence (Radiation measurement), Temperature effects, Vessels, Copper