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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.
L. EL-Guebaly, L. Mynsberge, ARIES-ACT Team
Fusion Science and Technology | Volume 67 | Number 1 | January 2015 | Pages 107-124
Technical Paper | doi.org/10.13182/FST14-791
Articles are hosted by Taylor and Francis Online.
The integration of nuclear assessment (neutronics, shielding, and activation) is an essential element to the success of any fusion design and represents a major issue for power plant studies in particular. High fidelity in nuclear results mandates performing state-of-the-art nuclear analyses. This has been achieved in recent years through coupling the computer-aided-design system directly with three-dimensional neutronics codes to preserve all geometrically complex design elements and speed up feedback and iterations. This paper outlines several major nuclear issues addressed for the recently completed ARIES-ACT1 tokamak conceptual power plant study. An integral nuclear approach was deemed necessary to deliver an optimal design. This approach considered the overall configuration, design requirements (including tritium self-sufficiency), smart selection of low-activation material for all components, radial build optimization and definition, and safety and environmental concerns. This paper reports the main results of this integral approach that aims at considering several effects that influence the global behavior of a complex power plant such as ARIES-ACT1.