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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.
Lawrence H. Porter, William E. Austin
Nuclear Technology | Volume 87 | Number 3 | November 1989 | Pages 595-608
Technical Paper | TMI-2: Remote Technology and Engineering / Nuclear Safety | doi.org/10.13182/NT89-A27711
Articles are hosted by Taylor and Francis Online.
As a result of the 1979 accident at Three Mile Island Unit 2, the reactor core was severely damaged. A major portion of the core relocated during the course of the accident through the core support assembly and into the lower head of the reactor vessel. As part of the program to recover from the accident, it was necessary to remove the core debris from the lower core support assembly (LCSA) and provide access to the reactor vessel lower head. A 3-yr planning, inspection, and research and development program was instituted to characterize the LCSA, identify and test techniques to remove the accident debris, produce detailed plans for defueling, and provide the equipment and facilities to implement the plan. The LCSA is being defueled using a “layered” approach, removing the maximum amount of the LCSA structure as practical. The stainless steel structure has been cut for removal using a core boring machine similar to oil drilling rig machinery and a specially designed plasma arc torch and manipulator control system. The lower grid top rib section and distributor plate have been removed, and forging removal operations have begun.