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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.
Lester M. Waganer, Richard J. Peipert, Jr., Xueren R. Wang, Siegfried Malang, ARIES Team
Fusion Science and Technology | Volume 54 | Number 3 | October 2008 | Pages 787-817
Technical Paper | Aries-Cs Special Issue | doi.org/10.13182/FST08-A1904
Articles are hosted by Taylor and Francis Online.
The goal of the ARIES compact stellarator is to define and assess a stellarator-based fusion power plant to provide electrical power as competitively as possible by balancing performance, cost, and plant availability. The traditional stellarator concepts are as compact as possible to reduce the plant capital costs, which are driven by the power core volume, weight, and cost. Different coil configurations are defined and assessed, trading plasma performance, power core design, access between the coils, and overall capital cost. Maintenance options are assessed and the port maintenance of first-wall/blanket and divertor modules is selected as the most feasible approach. Maintenance access is very important because the plasma-facing components have a limited lifetime. The available port access areas between the coils determine the maximum module envelope. With the maintenance approach selected, the frequency of maintenance determined, and module size defined, features of the maintenance approach are developed to maximize the power plant availability. After the preliminary maintenance approach, details for the power core components and facilities are finalized and a maintenance assessment is developed by analyzing the nominal times to conduct the maintenance actions. It is estimated that the ARIES-CS plant availability could reasonably be in the range of 85%.