Technologies researched under a GAIN NE Voucher for Liquid Metal Reactors
Oklo, Inc. (Santa Clara, CA) will partner with Idaho National Laboratory to complete pre-conceptual design work of an experimental test device that will be used in its first Aurora fast reactor to support irradiation testing of advanced fuels and materials.
Test Vehicle Development to Support Oklo’s Advanced Fuels Roadmap Read More »
For this project, ARC will work with Argonne National Laboratory (ANL) to enhance the SAS modeling capabilities for passive heat removal systems, including the generic RVACS model and the DRACS heat exchanger models. These enhancements will enable ARC to recover safety margins and have a better representation of the system’s response during long-term cooling events.
Improvements to Passive Heat Removal Systems in SAS4A/SASSYS-1 Read More »
Aalo will partner with Idaho National Laboratory (INL) to perform independent analyses on fuel performance using the BISON code as well as thermal-hydraulics using RELAP5-3D. This work will support the independent code-to-code verification to support Aalo’s future licensing efforts.
Independent Code-to-Code Verification of Aalo-1 Fuel and Core Performance Read More »
This project will leverage Pacific Northwest National Laboratory’s experience with high-temperature ultrasound to demonstrate feasibility for OLSHM of the Hydromine lead-cooled reactor heat exchanger for cracks and corrosion.
On-Line Lead/Water Heat Exchanger Sensor/System Feasibility, Hydromine Read More »
Oak Ridge National Laboratory (ORNL) worked with Westinghouse Electric Co. to optimize AFA steels for applications specific to LFRs, as reliable materials for key components such as fuel rod cladding, heat exchangers, reactor internals and the reactor vessel.
The objective of this project was to develop a computational capability for predicting radionuclide release from a broad spectrum of accidents that can be postulated to occur at liquid-metal-cooled reactor (LMR) facilities.
The objective of this project was to review Columbia Basin Consulting Group (CBCG)’s design concept for a leadbismuth-cooled fast reactor and thereafter to determine how the design might benefit from the functional containment concept, which allows the designer to take credit for a sequence of barriers to contain or confine radionuclides.
