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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.
T. Endo, N. Kobayashi, K. Goto, M. Yasuda, Y. Fujima
Fusion Science and Technology | Volume 43 | Number 3 | May 2003 | Pages 270-274
Technical Paper | Targets and Target Protection During Injection | doi.org/10.13182/FST03-A266
Articles are hosted by Taylor and Francis Online.
Experiments on the wall-thickness dependence of the cooling-induced deformation (CID) of polystyrene (PS) spherical shells were carried out. For the experiments, the PS shells were fabricated by the density-matched emulsion method using the hand-shaken microencapsulation technique. The number-averaged and weight-averaged molecular weights of the PS were Mn = 1.1 × 105 and Mw = 4.0 × 105, respectively. The diameter of the PS shells was ~400-550 m. To investigate the wall-thickness dependence of the CID, the wall thickness of the PS shells was varied between 5 and 60 m. In the experiments, the PS shells were cooled by using liquid nitrogen, and their images were captured at 0 and -190°C. For the investigation of the CID, two shapes of each shell that were measured at 0 and -190°C were compared. The thinner PS shells showed larger CID. The maximum deformation was almost 1% of the outer radius when the shell aspect ratio (outer radius)/(wall thickness) was higher than 20. The repeatability of the CID was studied, and the results implied that residual stress in the PS shells had an influence on the CID.