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Hilda B. Klasky
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Proceedings Papers

Application of the FAVOR-OCI Fracture Mechanics Computer Program to ASME Code Section XI, IWB-3610 Flaw Acceptance Criteria Evaluations

Terry L. Dickson, Paul T. Williams, B. Richard Bass, Hilda B. Klasky
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A069, July 15–20, 2018
Paper No: PVP2018-84412
DOI: https://doi.org/10.1115/PVP2018-84412
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Topics: Acceptance criteria, ASME Standards, Computer software, Fracture mechanics, Nuclear power stations, Computers, Fracture (Materials), Fracture (Process), Fracture toughness, Materials properties
Proceedings Papers

ORNL Evaluation of Safety Cases for Two Belgian Reactor Pressure Vessels Containing Quasi-Laminar Defects

Hilda B. Klasky, B. Richard Bass, Terry L. Dickson, Sarma B. Gorti, Randy K. Nanstad, Mikhail A. Sokolov, William L. Server, Paul T. Williams
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A045, July 16–20, 2017
Paper No: PVP2017-65305
DOI: https://doi.org/10.1115/PVP2017-65305
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Topics: Reactor vessels, Safety, Design, Fracture (Process), Transients (Dynamics), ASME Boiler and Pressure Vessel Code, ASME Standards, Coolants, Failure, Finite element analysis
Proceedings Papers

FAVOR Version 16.1: A Computer Code for Fracture Mechanics Analyses of Nuclear Reactor Pressure Vessels

B. Richard Bass, Paul T. Williams, Terry L. Dickson, Hilda B. Klasky
Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A002, July 16–20, 2017
Paper No: PVP2017-65262
DOI: https://doi.org/10.1115/PVP2017-65262
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Topics: Computers, Fracture mechanics, Nuclear reactors, Pressure vessels, Pressurized water reactors, Regulations, Boiling water reactors, Transients (Dynamics), Vessels, Fracture (Materials)
Proceedings Papers

LEAPOR: A Computer Code for Leakage-Rate Calculations for Cracks in Cooling Water Piping Systems

Paul T. Williams, B. Richard Bass, Terry L. Dickson, Hilda B. Klasky
Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A062, July 16–20, 2017
Paper No: PVP2017-65263
DOI: https://doi.org/10.1115/PVP2017-65263
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Topics: Computers, Cooling, Fracture (Materials), Leakage, Piping systems, Water, Flow (Dynamics), Pipes, Computer software, Design
Proceedings Papers

Assessment of a Stress-Free Temperature Model for Residual Stresses in Surface Cladding of a Reactor Pressure Vessel

B. Richard Bass, Paul T. Williams, Terry L. Dickson, Hilda B. Klasky
Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A058, July 16–20, 2017
Paper No: PVP2017-65255
DOI: https://doi.org/10.1115/PVP2017-65255
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Topics: Cladding systems (Building), Reactor vessels, Residual stresses, Stress, Temperature, Transients (Dynamics), Base metals, Finite element analysis, Drilling, Engineering models
Proceedings Papers

Analysis of Ductile Crack Growth in Pipe Test in STYLE Project

Shengjun Yin, Paul T. Williams, Hilda B. Klasky, B. Richard Bass
Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 487-496, July 15–19, 2012
Paper No: PVP2012-78518
DOI: https://doi.org/10.1115/PVP2012-78518
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Topics: Ductile fracture, Pipes, Finite element analysis, Stress, Collapse, Failure, Failure mechanisms, Fracture (Materials), Fracture mechanics, Modeling
Proceedings Papers

A Dislocation-Based Cleavage Initiation Model for Pressure Vessel Steels

Kristine B. Cochran, Marjorie Erickson, Paul T. Williams, Hilda B. Klasky, B. Richard Bass
Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 497-506, July 15–19, 2012
Paper No: PVP2012-78564
DOI: https://doi.org/10.1115/PVP2012-78564
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Topics: Dislocations, Pressure vessels, Steel, Particulate matter, Stress, Fracture (Materials), Computers, Fracture toughness, Microcracks, Brittleness
Proceedings Papers

ORNL Pre-Test Analyses of a Large-Scale Experiment in STYLE

Paul T. Williams, Shengjun Yin, Hilda B. Klasky, B. Richard Bass
Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 283-292, July 17–21, 2011
Paper No: PVP2011-57373
DOI: https://doi.org/10.1115/PVP2011-57373
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Topics: Experimental design, Finite element analysis, Fracture (Materials), Fracture mechanics, Modeling, Nuclear industry, Nuclear reactor coolants, Numerical analysis, Pipes, Pressure