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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.
Ruixuan Han, Liucheng Liu, Rui Tu, Wei Xiao, Yingying Li, Huailin Li, Dan Shao
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 192-203
Technical Paper | doi.org/10.13182/NT15-109
Articles are hosted by Taylor and Francis Online.
Iodine atom interstitial configurations and diffusion in bulk β-SiC and α-Zr are calculated using first-principles calculations and the nudged elastic band method. The formation energy of an I interstitial in bulk silicon carbide (SiC) is ten times higher than that of an I interstitial in bulk Zr. The I interstitial is very difficult to introduce into bulk SiC compared with the doping process in bulk Zr. The diffusion mechanisms of an I atom in SiC and Zr are exchange mechanisms. Iodine interstitial diffusion in bulk SiC is roughly an isotropic process along a path that is a series of combinations of ISi → Ic and Ic → ISi, with a diffusion barrier of 1.20 eV and an attempt-to-diffuse frequency Γ0 25.12 THz. Meanwhile, I interstitial diffusion in bulk Zr is an anisotropic process. An I interstitial atom diffuses mainly between two Zr atom [0001] layers along a zigzag path with a diffusion barrier of 0.16 eV and an attempt-to-diffuse frequency Γ0 = 2.88 THz. In general, the diffusion rate of an I interstitial in bulk SiC is lower than that in bulk Zr in the temperature range from 290 to 3000 K. The defect effect on I diffusion is an interesting topic for future study.