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Proceedings Papers

Investigation of the Internal Impact During a 9 M Drop Test of an Accident-Safe Waste Package

Marko Nehrig, Robert Scheidemann, Frank Wille, Viktor Ballheimer

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A023, July 13–15, 2021

Paper No: PVP2021-60996

DOI: https://doi.org/10.1115/PVP2021-60996

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Topics: Accidents, Regulations, Safety, Containment systems, Design, Heat conduction, Leakage, Radioactive substances, Stress, Temperature

Proceedings Papers

Technical Basis Summary for Code Case N-860: Inspection Requirements and Evaluation Standards for Spent Nuclear Fuel Storage and Transportation Containment Systems

John E. Broussard, III

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A061, July 13–15, 2021

Paper No: PVP2021-64176

DOI: https://doi.org/10.1115/PVP2021-64176

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Topics: Containment systems, Inspection, Spent fuel storage, Spent nuclear fuels, Stress corrosion cracking, Transportation systems, In-service inspection, Acceptance criteria, ASME Boiler and Pressure Vessel Code, Fracture (Materials)

Proceedings Papers

Numerical Simulation and Measurements of Reaction Load for an Impulsively Loaded Pressure Vessel

Matthew Fister, Kevin Fehlmann, Dusan Spernjak

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T05A015, July 13–15, 2021

Paper No: PVP2021-62085

DOI: https://doi.org/10.1115/PVP2021-62085

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Topics: Computer simulation, Containment, Explosives, Pressure vessels, Shock (Mechanics), Stress, Vessels, Uncertainty, Design, Physics experiments

Proceedings Papers

Design and Testing of an Explosively Loaded Pressure Vessel System for Proton Radiography

Dusan Spernjak, Kevin Fehlmann, Devin Cardon, Nathan Yost, Dallas Hill, Anna Llobet

Proc. ASME. PVP2020, Volume 5: High Pressure Technology, V005T05A009, August 3, 2020

Paper No: PVP2020-21647

DOI: https://doi.org/10.1115/PVP2020-21647

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Topics: Design, Physics, Pressure vessel systems, Protons, Shock (Mechanics), Testing, Vessels, Pressure, Explosives, Imaging

Proceedings Papers

New Code Case Development for the Mitigation of PWSCC and CISCC in ASME Section III Components by Advanced Surface Stress Improvement Technology

Sungwoo Cho, Nicholas Mohr, Young Sik Pyun, Auezhan Amanov, John Broussard

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A086, July 14–19, 2019

Paper No: PVP2019-93232

DOI: https://doi.org/10.1115/PVP2019-93232

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Topics: Stress, Stress corrosion cracking, Construction, Maintenance, Residual stresses, Acceptance criteria, Containment systems, Electricity (Physics), Manufacturing, Nuclear power stations

Proceedings Papers

Application of Leakage Rates Measured on Scaled Cask or Component Models to the Package Containment Safety Assessment

Annette Rolle, Viktor Ballheimer, Tino Neumeyer, Frank Wille

Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A033, July 15–20, 2018

Paper No: PVP2018-84089

DOI: https://doi.org/10.1115/PVP2018-84089

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Topics: Containment, Leakage, Safety, Containment systems, Accidents, Deformation, Design, Radioactive wastes, Spent nuclear fuels, Storage

Proceedings Papers

Bounding Surface Flaw Configuration Susceptible to Stress Corrosion Cracking Under Welding Residual Stress in a Multiple-Purpose Canister

Poh-Sang Lam, Robert L. Sindelar, Andrew J. Duncan, Joe T. Carter

Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A063, July 16–20, 2017

Paper No: PVP2017-66055

DOI: https://doi.org/10.1115/PVP2017-66055

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Topics: Stress, Stress corrosion cracking, Welding, Fracture (Materials), Acceptance criteria, Containment systems, In-service inspection, Mechanical engineers, Spent fuel storage, Spent nuclear fuels

Proceedings Papers

Behavior of Wood Filled Impact Limiters During the IAEA Thermal Test

Martin Feldkamp, Marina Erenberg, Marko Nehrig, Claus Bletzer, André Musolff, Thorsten Schönfelder, Frank Wille

Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A038, July 16–20, 2017

Paper No: PVP2017-65721

DOI: https://doi.org/10.1115/PVP2017-65721

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Topics: Wood products, Damage, Safety, Combustion, Cushioning materials, Containment, Fire, Fire testing, Mechanical testing, Radioactive substances

Proceedings Papers

Methodological Aspects for Numerical Analysis of Lid Systems for SNF and HLW Transport Packages

Konrad Linnemann, Viktor Ballheimer, Jens Sterthaus, Frank Wille

Proc. ASME. PVP2014, Volume 3: Design and Analysis, V003T03A016, July 20–24, 2014

Paper No: PVP2014-28304

DOI: https://doi.org/10.1115/PVP2014-28304

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Topics: Numerical analysis, Transport packages, Containment systems, Accidents, Design, Finite element analysis, Gaskets, Stress, Deformation, Materials research

Proceedings Papers

Numerical Approach for Containment Assessment of Transport Packages Under Regulatory Thermal Test Conditions

Jens Sterthaus, Viktor Ballheimer, Claus Bletzer, Konrad Linnemann, Marko Nehrig, Frank Wille

Proc. ASME. PVP2014, Volume 3: Design and Analysis, V003T03A100, July 20–24, 2014

Paper No: PVP2014-28199

DOI: https://doi.org/10.1115/PVP2014-28199

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Topics: Containment, Transport packages, Deformation, Finite element analysis, Sealing (Process), Accidents, Compression, Containment systems, Finite element model, Fire

Proceedings Papers

Containment of Low-Level Radioactive Waste at the DOE Saltstone Disposal Facility

Jeff Jordan, Greg Flach

Proc. ASME. PVP2012, Volume 7: Operations, Applications and Components, 295-298, July 15–19, 2012

Paper No: PVP2012-78797

DOI: https://doi.org/10.1115/PVP2012-78797

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Topics: Containment, Containment systems, Design, Groundwater, Modeling, Radioactive wastes, Rivers, Soil, Storage, Waste disposal

Proceedings Papers

Failure Frequency Estimates for Boiling Water Reactor Pressure Vessels

F. A. Simonen, S. R. Gosselin, J. E. Rhoads, A. T. Chiang

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 349-361, July 18–22, 2010

Paper No: PVP2010-25232

DOI: https://doi.org/10.1115/PVP2010-25232

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Topics: Boiling water reactors, Failure, Pressure vessels, Vessels, Rupture, Pressurized water reactors, Accidents, Damage, Accounting, Containment systems

Proceedings Papers

Status of Code Development for ASME B&PV Code, Section III, Division 3

D. Keith Morton, Gerald M. Foster, R. Howard Smith, Gary R. Cannell

Proc. ASME. PVP2008, Volume 1: Codes and Standards, 261-265, July 27–31, 2008

Paper No: PVP2008-61576

DOI: https://doi.org/10.1115/PVP2008-61576

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Topics: Acceptance criteria, Containment systems, Mechanical engineers, Spent nuclear fuels, Transportation systems, Waste handling

Proceedings Papers

Composite Vessels for Containment of Extreme Blast Loadings

John W. Pastrnak

Proc. ASME. PVP2004, Emerging Technology in Fluids, Structures, and Fluid Structure Interactions: Volume 2, Dynamics of Explosive Detonation, Materials and Structures, Structural Mechanics and Design, 25-26, July 25–29, 2004

Paper No: PVP2004-2876

DOI: https://doi.org/10.1115/PVP2004-2876

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Topics: Composite materials, Containment, Vessels, Explosives, Design, Aluminum, Containment vessels, Explosions, Hazardous substances, Imaging

NARROW

Investigation of the Internal Impact During a 9 M Drop Test of an Accident-Safe Waste Package

Technical Basis Summary for Code Case N-860: Inspection Requirements and Evaluation Standards for Spent Nuclear Fuel Storage and Transportation Containment Systems

Numerical Simulation and Measurements of Reaction Load for an Impulsively Loaded Pressure Vessel

Design and Testing of an Explosively Loaded Pressure Vessel System for Proton Radiography

New Code Case Development for the Mitigation of PWSCC and CISCC in ASME Section III Components by Advanced Surface Stress Improvement Technology

Application of Leakage Rates Measured on Scaled Cask or Component Models to the Package Containment Safety Assessment

Bounding Surface Flaw Configuration Susceptible to Stress Corrosion Cracking Under Welding Residual Stress in a Multiple-Purpose Canister

Behavior of Wood Filled Impact Limiters During the IAEA Thermal Test

Methodological Aspects for Numerical Analysis of Lid Systems for SNF and HLW Transport Packages

Numerical Approach for Containment Assessment of Transport Packages Under Regulatory Thermal Test Conditions

Containment of Low-Level Radioactive Waste at the DOE Saltstone Disposal Facility

Failure Frequency Estimates for Boiling Water Reactor Pressure Vessels

Status of Code Development for ASME B&PV Code, Section III, Division 3

Composite Vessels for Containment of Extreme Blast Loadings

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