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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.
H. Huang, H. W. Xu, K. P. Youngblood, D. R. Wall, R. B. Stephens, K. A. Moreno, A. Nikroo, K. J. Wu, M. Wang, A. V. Hamza
Fusion Science and Technology | Volume 63 | Number 2 | March-April 2013 | Pages 190-201
Technical Paper | Selected papers from 20th Target Fabrication Meeting, May 20-24, 2012, Santa Fe, NM, Guest Editor: Robert C. Cook | doi.org/10.13182/FST13-TFM20-24
Articles are hosted by Taylor and Francis Online.
The National Ignition Facility point design uses a five-layer capsule to modify the X-ray absorption in order to achieve optimized shock timing. A stepwise copper dopant design defines the layer structure; however, the as-deposited Cu distribution is significantly altered during the CH mandrel removal by pyrolysis. The changes are significant: (a) Cu diffuses on average several microns, a distance more than an order of magnitude larger than predicted from the bulk diffusion data, and (b) the Cu distribution, as a result of diffusion, is highly heterogeneous, introducing a local variation of [approximately]0.06 at. % near the original layer interface. In this study, we developed quantitative techniques to measure Cu diffusion and explored its correlation to beryllium microstructures. Plausible diffusion mechanisms and mitigation methods will be discussed. These findings will enable more accurate evaluation of the expected target performance.