GAIN-EPRI-NEI Clean Nuclear Energy for Industry Workshop
April 16, 2020
The purpose of the GAIN-EPRI-NEI ENERGY: Clean Nuclear Energy for Industry Webinar was to develop active engagement between Energy End-Users and Advance Nuclear Developers leading to a credible, shared vision for the use of nuclear-generated heat to meet future heat, steam and electricity needs. The webinar objectives were to:
Identify end-user needs for power, heat, steam, etc., including reliability requirements.
Inform end-users about the capabilities and timelines for advanced reactors.
Establish connections between the advanced nuclear technology developers and energy end-users.
Fuel Cladding Materials for the Westinghouse Lead Fast Reactor
Structural and Salt Facing Material Needs Molten Chloride Fast Reactor
Advanced Reactor Safeguards: Nuclear Material Control and Accounting for Pebble Bed Reactors
Assessing Fuel Cycle Options for Elysium Molten Chloride Salt Fast Reactor from Spent Nuclear Fuel, Plutonium, and Depleted Uranium
Development and Testing of Alumina-forming Austenitic Stainless Steels for Lead Fast Reactor Application
Methodology for Meeting Containment System Principal Design Criteria for Heavy Metal Fast Reactor Systems
Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel
Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel
Development of an Integrated Mechanistic Source Term Assessment Capability for Lead- and Sodium-Cooled Fast Reactors
Development of an Integrated Mechanistic Source Term Assessment Capability for Lead- and Sodium-Cooled Fast Reactors
Risk-Informed Mechanistic Source Term Calculations for a Compact Fast Reactor
DOE Advanced M&S Program for Fast Reactor Applications Presentation – July 2019
GAIN-NEI Fast Reactor Working Group Workshop Presentation – July 2019
ADDITIONAL RESOURCES
Fuel Cladding Materials for the Westinghouse Lead Fast Reactor
Structural and Salt Facing Material Needs Molten Chloride Fast Reactor
Advanced Reactor Safeguards: Nuclear Material Control and Accounting for Pebble Bed Reactors
Assessing Fuel Cycle Options for Elysium Molten Chloride Salt Fast Reactor from Spent Nuclear Fuel, Plutonium, and Depleted Uranium
Development and Testing of Alumina-forming Austenitic Stainless Steels for Lead Fast Reactor Application
Methodology for Meeting Containment System Principal Design Criteria for Heavy Metal Fast Reactor Systems
Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel
Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel
Development of an Integrated Mechanistic Source Term Assessment Capability for Lead- and Sodium-Cooled Fast Reactors
Development of an Integrated Mechanistic Source Term Assessment Capability for Lead- and Sodium-Cooled Fast Reactors
Risk-Informed Mechanistic Source Term Calculations for a Compact Fast Reactor
DOE Advanced M&S Program for Fast Reactor Applications Presentation – July 2019
GAIN-NEI Fast Reactor Working Group Workshop Presentation – July 2019
Click on the bulleted links below for additional background information: