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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.
Anil Kumar, Cherif Sahraoui
Fusion Science and Technology | Volume 13 | Number 3 | March 1988 | Pages 484-494
Technical Paper | Alpha-Particle Workshop / Blanket Engineering | doi.org/10.13182/FST88-A25126
Articles are hosted by Taylor and Francis Online.
Reaction rates of 115In(n, n′) and 90Zr(n,2n) were measured on various axial positions inside single slabs of 18-cm-thick beryllium and 15-cm-thick lead kept in front of a Haefely deuterium-tritium neutron generator. These experimental axial activity profiles, and those for the zirconium/indium ratio, are compared to those computed using the two-dimensional discrete ordinates code DOT 3.5 coupled to a compatible first-collision source evaluator code GREATUNCL. Generally, a satisfactory agreement is seen between these profiles for both beryllium and lead slabs.
