SAM: A Modern System Code for Advanced Non-LWR Safety Analysis
The System Analysis Module (SAM), developed at Argonne National Laboratory and by collaborators at other organizations, is for advanced non–light water reactor safety analysis. SAM aims to provide fast-running, modest-fidelity, whole-plant transient analysis capabilities that are essential for fast-turnaround design scoping and engineering analyses of advanced reactor concepts. To facilitate code development, SAM utilizes the […]
Molten Salt Tritium Transport Experiment: A Versatile Fluoride Salt Loop for Validation of Tritium Transport Phenomena
Tritium is generated in Molten Salt Reactors (MSRs) from neutron capture by lithium and other constituents of the molten salt FLiBe. Tritium is a unique radionuclide as it readily permeates through hot structural materials. Thus, any material in contact with tritium laden molten salt is a potential pathway for release. Understanding tritium transport and devising […]
Sodium-Cooled Fast Reactor Reference Plant Model
This report details the progress of INL on the creation of a reference plant multiphysics model for the ABTR. The model was developed within Task 13 of the NRC project “Development and Modeling Support for Advanced Non-Light Water Reactors” and is an extension of the reference plant developed in Task 4b. Several improvements were made […]