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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.
August W. Cronenberg, E. L. Tolman
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 273-282
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27654
Articles are hosted by Taylor and Francis Online.
Inspection of the Three Mile Island Unit 2 (TMI-2) reactor vessel has yielded a wealth of information on core melt debris thermal interactions with vessel internal structures. The observed damage state of such structures is summarized and an analysis is presented to further the understanding of governing physical processes. Specifically, thermal damage is assessed for the baffle plates surrounding the core periphery, the core former plates, the bottom head instrument penetrations, and the lower head. Analysis indicates that differences in damage characteristics to such structures are due largely to differences in contact time with molten corium, the heat capacity of the various structures, and exposure to coolant. Vessel and debris examinations corroborate the present understanding of melt debris/structural interactions during the melt relocation phase of the TMI-2 accident.