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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.
Giovanni Dell'Orco, Warren Curd, Fabien Berruyer, Seokho Kim, Roy Shearin, Juan Ferrada
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 100-104
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12334
Articles are hosted by Taylor and Francis Online.
ITER is a joint international fusion facility to demonstrate the scientific and technological feasibility of fusion power for future commercial electric power facilities. ITER is designed to reject all the heat generated in the plasma and transmitted to the in-vessel components through the Tokamak Cooling Water System (TCWS) to the intermediate closed loop Component Cooling Water System (CCWS) and then to the environment via the open Heat Rejection System (HRS) and Cooling Towers. At the present the main in-vessel components as First Wall-Blanket (FW-BLK) and the Divertor (DIV) are cooled via four separated Primary Heat Transfer Systems (PHTSs). This paper describes the proposal to integrate the PHTS for the FW-BLK and DIV in a common loop to improve the availability and reliability of the cooling system. Furthermore, the paper presents the new thermal hydraulic design parameters, the relevant Process Flow Diagram (PFD) and a study for the new arrangements of the piping in the TCWS vault. Some associated issues for safety accidental scenarios are planned to be solved before the final acceptance of the proposal in the baseline design.
