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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
G. Anand, R. N. Christense
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 287-294
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34725
Articles are hosted by Taylor and Francis Online.
An emergency core cooling system incorporating a bistable convection loop (BCL) for current passive liquid-metal-cooled reactors is proposed. The system has two stable operating modes. During the off mode, the system is in a pure conduction mode and transfers very little heat. In the on mode, the system switches to the low-resistance configuration of a closed natural convection loop and transfers significant amounts of heat. The switching occurs passively because of changes in the reactor temperature. Theoretical and experimental analysis shows that a BCL designed to remove 7% of peak reactor power in the on mode loses only 0.0007% in the off mode, yielding a ratio of 10 000:1.