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Latest News
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.
M. S. Tillack, X. R. Wang, D. Navaei, H. H. Toudeshki, A. F. Rowcliffe, F. Najmabadi, ARIES Team
Fusion Science and Technology | Volume 67 | Number 1 | January 2015 | Pages 49-74
Technical Paper | doi.org/10.13182/FST14-790
Articles are hosted by Taylor and Francis Online.
ARIES-ACT1 is the latest in a series of tokamak power plant designs that capitalize on the high-temperature capabilities and attractive safety and environmental characteristics of SiC composites coupled with a self-cooled lead-lithium breeder. This combination offers both design simplicity and high performance, capable of operating at very high coolant outlet temperature in a moderately high-power-density device. Blankets are supported within a poloidally continuous He-cooled steel structural ring, which adds robustness and minimizes loads on the SiC modules. In order to withstand high local surface heat flux in the divertor (of the order of 14 MW/m2 time averaged), a helium-cooled tungsten-alloy divertor was adopted. About 25% of the total “high-grade” heat is thus removed by helium, to be combined with the blanket heat in order to feed the power cycle. In addition to the in-vessel power-producing elements of the design, this paper also summarizes the key features and analysis of the vacuum vessel and power conversion system.