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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.
Wenxing Xia, Li Yang, Kun Zhang, Pingni He, Lei Shu, Lei Han, Xiaochun Ma, Zhiyan Zhang, Zhi Cao, F. Gou
Fusion Science and Technology | Volume 75 | Number 2 | February 2019 | Pages 104-111
Technical Paper | doi.org/10.1080/15361055.2018.1533618
Articles are hosted by Taylor and Francis Online.
The corrosion behaviors of 316L stainless steel welds in stagnant liquid lithium and lithium with 0.2%H at 325°C for 1000 h was investigated by using weight loss method, scanning electron microscopy, energy dispersive spectroscopy, X-ray diffraction, and laser-induced breakdown spectroscopy. After liquid Li corrosion, a large number of (M)23C6 and NiCx particles (sizes of 1 ~ 2 μm) were found on the weld surface, while almost no such particles were found on the weld surface after corrosion in liquid Li with 0.2%H. The corrosion rates of welds were about 4.10 × 10−3 and 6.65 × 10−3 g · m−2 · h−1 in liquid Li and Li with 0.2%H, respectively, while the penetration depth of Li increased by 1.375 times after adding 0.2%H to Li. It was found that the penetration depth of Li was basically consistent with the dissolution depth of Cr, and the dissolution depth of Cr was larger than that of Ni and Fe in liquid Li and Li with 0.2%H.