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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.
Sehila M. Gonzalez De Vicente, Sergei Dudarev, Michael Rieth
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 38-45
Technical Paper | doi.org/10.13182/FST13-764
Articles are hosted by Taylor and Francis Online.
The Fusion Materials Topical Group (FMTG) coordinates, under the European Fusion Development Agreement (EFDA), the EU effort on the development of structural and protection materials for the very demanding operating conditions of a future DEMO reactor. The reference documents for this program are the European Roadmap for Fusion and the Materials Assessment Group (MAG) report. The FMTG work or EFDA work is structured as follows: a) Integrated radiation effects modelling and experimental validation: focused on the development of a conceptual and quantitative framework for the interpretation of experimental tests on steels and iron-based alloys and tungsten and tungsten alloys and predicting the performance of these materials under DEMO-relevant operating conditions. b) High heat flux materials: focused on the development of materials for armour applications (W alloys), structural applications for low and high temperature cooling concepts (Cu-based alloys, W-based alloys), materials technologies (joining, fabrication), and testing of prototype of cooling structures. c) Nano-structured oxide dispersion strengthened (ODS) ferritic steel development: focused on the development of an ODS ferritic steel with high tensile and creep strength and sufficient ductility and fracture toughness up to about 750°C, as well as good radiation resistance. d) Materials database status and needs for DEMO conceptual design activities: focused on the assessment and analysis of fusion materials available data, identifying areas of uncertainties and conditions (relevant to the design) where data are either missing or unreliable.