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Robert Sindelar
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Proceedings Papers

Development of an Apparatus for Chloride Induced Stress Corrosion Cracking Test Using Immersion Method With Constant Displacement Condition

Jae-Yoon Jeong, Myeong-Woo Lee, Yun-Jae Kim, Robert Sindelar, Andrew Duncan
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A051, July 14–19, 2019
Paper No: PVP2019-93922
DOI: https://doi.org/10.1115/PVP2019-93922
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Topics: Displacement, Spent nuclear fuels, Stainless steel, Stress corrosion cracking
Proceedings Papers

Crack Growth Rate Model for CISCC of Stainless Steel Canisters

John E. Broussard, III, Charles Bryan, Robert Sindelar, Poh-Sang Lam
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A054, July 14–19, 2019
Paper No: PVP2019-94055
DOI: https://doi.org/10.1115/PVP2019-94055
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Topics: Fracture (Materials), Stainless steel, Stress corrosion cracking, Tension, Aerosols, ASME Boiler and Pressure Vessel Code, Cracking (Materials), Deliquescence, Fracture (Process), Spent nuclear fuels
Proceedings Papers

Experience With Damaged Spent Nuclear Fuel at U.S. DOE Facilities

Brett Carlsen, Denzel Fillmore, Roger L. McCormack, Robert Sindelar, Timothy Spieker, Eric Woolstenhulme
Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 879-899, July 17–20, 2006
Paper No: ICONE14-89319
DOI: https://doi.org/10.1115/ICONE14-89319
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Topics: Spent nuclear fuels, Storage, Design