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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.
Hans U. Borgstedt, Jürgen Konys
Fusion Science and Technology | Volume 33 | Number 1 | January 1998 | Pages 68-73
Technical Paper | doi.org/10.13182/FST98-A17
Articles are hosted by Taylor and Francis Online.
Reactions between the vanadium-base alloy V-1 Si-3 Ti and lithium were studied at 550°C in a forced convection loop made of stabilized austenitic stainless steel. Preheating the lithium in contact with a titanium sponge reduced the nitrogen and carbon levels below 100 wppm. In spite of the low concentrations of nonmetallic elements, the vanadium alloy picked up these contaminants, producing a hardened surface layer. Nitrogen concentrations in the range of 10 to 70 wppm significantly influenced the dissolution rate of the solid alloy. Carbon uptake did not reach these levels. Surfaces of the alloy remained unprotected at the lowest nitrogen levels in the lithium. At higher contents, a protecting compound was detected at the surface of the alloy, reducing the dissolution rate during the corrosion test. Dissolution of vanadium and the minor alloying elements became evident when nitrogen concentration was increased further. Material losses from V-1 Si-3 Ti was only one-tenth of that seen from either austenitic or ferritic stainless steels at the same temperature and flow velocity.