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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. J. Renk, B. Williams, L. El-Guebaly, A. Jaber
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 570-578
IFE Design & Technology | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12444
Articles are hosted by Taylor and Francis Online.
The level of energy deposition on future inertial fusion energy (IFE) reactor first walls, particularly in direct-drive scenarios, makes the ultimate survivability of such wall materials a challenge. We investigate the survivability of three-dimensional (3-D) dendritic materials fabricated by chemical vapor deposition (CVD), and exposed to repeated intense helium beam pulses on the RHEPP-1 facility at Sandia National Laboratories. Prior exposures of flat materials have led to what appears to be unacceptable mass loss on timescales insufficient for economical reactor operation. Two potential advantages of such dendritic materials are a) increased effective surface area, resulting in lowered fluences to most of the wall material surface, and b) improvement in materials properties for such micro-engineered metals compared to bulk processing. Several dendritic fabrications made with either tungsten and tungsten with rhenium show little or no morphology change after up to 800 pulses of 1 MeV helium at reactor-level thermal wall loading. Since the rhenium is added in a thin surface layer, its use does not appear to raise environmental concerns for fusion designs.