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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.
J. Bourdon, F. Mannone, A Aytekin, I.S. Wheelton
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 352-358
Safety; Measurement and Accountability; Operation and Maintenance; Application | doi.org/10.13182/FST92-A29770
Articles are hosted by Taylor and Francis Online.
The European Tritium Handling Experimental Laboratory (ETHEL) is a new tritium facility at the Commission of the European Community's Joint Research Centre, Ispra Site. The Laboratory, which is foreseen to commence radioactive operations in 1992, has the basic research goal of investigating and developing safe tritium handling techniques. Therefore, during the design and construction of the facility much emphasis was given to provide research personnel with a flexible tool for performing experimental work under safe conditions. This paper describes the main types of containment in which tritium research will be performed and the various gaseous detritiation systems which serve these containments.