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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.
Keiji Miyazaki, Kensuke Konishi, Yoshihisa Gonno, Shoji Inoue, Masaki Saito
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 969-975
Blanket Technology | doi.org/10.13182/FST91-A29468
Articles are hosted by Taylor and Francis Online.
For reducing the liquid metal MHD pressure drop of the first wall cooling, a NaK experimental study was made on the effects of the electrical insulation of a rectangular duct. Three inner surfaces of a 2.1 mm thick 304-SS rectangular duct of 20.5 mm × 45.5 mm inner cross-section was coated by 1.3 mm thick FRP plates, remaining one of the 45.5 mm wide faces uninsulated to simulate the plasma facing first wall. The magnetic field was mainly applied in parallel to the uninsulated face. The results are summarized as follows. (1) The MHD pressure drop gradient is proportional to the mean flow velocity U and also to the magnetic flux density B. (2) It is about 2.3 times higher than the value predicted by Shercliff's theory for a completely insulated rectangular duct. (3) It is largely reduced, for the same velocity, down to 7.7% at B= 1.0 T and 5.1% at B= 1.5 T in comparison with the uninsulated duct. These results are encouraging for applying to fusion power reactors.
