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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.
Ihor O. Bohachevsky, Ronald N. Kostoff
Fusion Science and Technology | Volume 2 | Number 4 | October 1982 | Pages 687-699
Technical Paper | Blanket Engineering | doi.org/10.13182/FST82-A20807
Articles are hosted by Taylor and Francis Online.
Cyclic thermal loads and stresses in two critical components of fusion reactors, including fusion-fission hybrids, are modeled and calculated. The two critical components are the solid wall adjacent to the fusion plasma (“first wall”) and the fissile fuel elements in the high-power density region of the blanket. These two components exemplify two limiting cases of thermal loading: The first-wall loads are generated by predominantly shallow energy deposition that may be approximated with a flux across the surface and the fuel elements loads are generated by volumetric heating. Two approaches are used to solve the heat conduction equation and to calculate the resulting stresses in terms of system parameters. The first is expansion into Fourier series and determination of periodic solutions; the second is analysis and superposition of single-pulse responses weighted with appropriate time delay and decay factors. Approximate closed-form expression for temperature excursions and thermal stresses are derived; these expressions may be evaluated conveniently and rapidly for comparison of different systems. The results provide a quantitative basis for trade-off studies and comparative assessments of different fusion reactor systems.