Concurrent Technical Session – REG: Benefits of International Collaboration
9:00 AM - 9:20 AM CST
Multilateral approval of a SCO-III (three spent steam generator lower parts from EDF Fessenheim Nuclear Power Plant) multimodal shipment – French, Belgian, Dutch and German Collaboration
ASME's Guidance Document on Use of Explicit Finite Element Analysis for the Evaluation of Radioactive Material Transport Packages and Storage Casks in Energy-Limited Impact Events
Concurrent Technical Session – OPS: Preparation for Long Term Storage
2:00 PM - 3:20 PM CST
Concurrent Technical Session – OPS: Preparation for Long Term Storage
Location: Conference Room 1-4
2:00 PM - 2:20 PM CST
Leveraging Historical Precedent for the Transportation of Irradiated Sodium-bonded Metal Fuel: Lessons from Experimental Breeder Reactor-II, Fast Flux Test Facility, and Fermi-1
Review and Revision of the IAEA Regulations for the Safe Transport of Radioactive Material, 2018 Edition, IAEA Safety Standards Series No. SSR-6 (Rev. 1)
Location: Conference Room 16-17
Presenting Author: Eric H. Reber, n/a – International Atomic Energy Agency
4:20 PM - 4:40 PM CST
SSR-6 is more than a product of IAEA – the basic stance to conduct the review and revision process of the IAEA Transport Regulations
Location: Conference Room 16-17
Presenting Author: Makoto Hirose, n/a – National Maritime Research Institute
4:40 PM - 5:00 PM CST
Thoughts on an Effective Process for Reviewing and Revising SSR-6
Location: Conference Room 16-17
Presenting Author: Ingo Reiche, n/a – Federal Office for the Safety of Nuclear Waste Management (BASE)
Corrosion Behavior of Cold-Sprayed and Additive Friction Stir Deposited 304L Stainless Steel for Spent Nuclear Fuel Dry Storage Canisters and the Effects of Mechanical Surface Treatments
Concurrent Technical Session – DESIGN: Structural Analysis of Specific Components
3:40 PM - 5:20 PM CST
Concurrent Technical Session – DESIGN: Structural Analysis of Specific Components
Location: Salons C-D
3:40 PM - 4:00 PM CST
Nuclear Waste Package Transport Frame Design Optimisation Using Finite Element Analysis To Design An Engineered Weak Link and To Improve Weld Capacity And Fatigue Life
Enhancement of Leak Testing with Advanced Weather and Vacuum Conditioning Equipment Supports Transitioning from Pressure Change to Helium Mass Spectrometer Methods
Gas Leakage Rates at the Containment Boundary of Type B RAM Transportation Packages Derived from the Bhatnagar-Gross-Krook (BGK) Model of the Boltzmann Equation
SURVEILLANCE DETECTION FOR TRANSPORTATION OPERATIONS PERSONNEL TO PREVENT HIJACKING, THEFT, SABOTAGE, AND MALICIOUS SECURITY EVENTS DURING TRANSPORTING NUCLEAR MATERIAL
Location: Conference Room 20-21
Presenting Author: Mohamad Zineddin – Oak Ridge National Laboratory
4:40 PM - 5:00 PM CST
Off-Site Source Recovery Program: Mitigation of Risks to Program Missions Due to Threats Posed by Insiders
An Overview of Nigeria's Bilateral Collaboration with the U.S. Department of Energy's National Nuclear Security Administration (NNSA) Office of Radiological Security (ORS)
