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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.
Herbert W. Kirkland, Marc A. Nemser, William M. Laney
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 932-945
Technical Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27687
Articles are hosted by Taylor and Francis Online.
One of the significant tasks facing defuelers in the aftermath of the Three Mile Island Unit 2 (TMI-2) accident has been the dismantlement and removal of the severely damaged reactor core. One of the most effective tools utilized to loosen and pulverize the debris bed and the once-molten, resolidified core was the core bore machine (CBM). This machine was very successful during the core stratification sampling program, which extracted core samples from the postaccident reactor core for data acquisition and analysis. The machine was later used to drill hundreds of holes in the hard, resolidified layer in the effort to advance the defueling process by pulverizing the core. Once again, the CBM proved effective. With all damaged fuel assemblies removed from the vessel, the majority of the fuel debris remaining in the reactor vessel is located in the lower core support assembly (LCSA) and the lower head of the reactor vessel. The only conceivable method of accessing the fuel remnants and debris is by severing and removing the massive stainless steel plates of the LCSA that inhibit deployment of defueling tools and equipment. A comprehensive program to remove the LCSA was initiated that incorporated the CBM and a plasma arc cutting system that could, in combination, be effective in removing the entire assembly. This paper describes the drilling equipment and the methods used to successfully remove the lower grid rib section utilizing the CBM as it has proved to be a viable technique for remotely cutting underwater stainless steel structures.