An example cutaway of a disposal facility similar to Monticello. (Photo: Craig Benson)
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) has held another presentation in its monthly Community of Practice (CoP) series. Former RP3C chair N. Prasad Kadambi opened the meeting with brief introductory remarks about the RP3C and the need for new approaches to nuclear design that go beyond conventional and deterministic methods. He then welcomed this month’s speaker: Craig Benson from the University of Wisconsin–Madison, who presented “Natural Systems Approach for Closure of Uranium Mill Tailing Facilities.”
Figure showing the nine steps of the demonstration example’s RIPB design process.
Uranium chloride fuel salt. (Photo: INL)
Scientists at Idaho National Laboratory continue to make progress on the Molten Chloride Reactor Experiment (MCRE), which entails research and development for the first operational advanced nuclear reactor to use a mixture of molten chloride salt and uranium as fuel and coolant. The experiment is evaluating the safety and physics of the molten chloride fast reactor that Southern Company and TerraPower are planning to build.