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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.
J. G. Murray/K. E. Rothe, George Bronner
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1486-1490
Power Conversion, Instrumentation, and Control | doi.org/10.13182/FST83-A23066
Articles are hosted by Taylor and Francis Online.
The energy loss in a torus vessel during startup is now an important factor in a power-producing tokamak design. The torus design cannot be based on a system which minimizes the conductivity with resistive structures as in present experimental devices. If the resistivity of the torus is too high, the reactors are subject to damage from an uncontrolled fast shutdown such as a disruption. The thermal and magnetic stored energy due to the plasma current loop is several hundred megajoules, which can produce melting of the torus wall. To prevent excessive damage, a low resistance passive circuit must be provided close to the plasma edge. Another desirable design feature is to make all vacuum seals as far away from the plasma as practical. Thus, the reactor torus designs need an inner low resistance shell and an outer high resistance shell. In addition, the superconducting dewar and coil support structures provide paths for toroidal currents to flow. The calculations provided in this paper can be used to determine the size and cost of the systems as a function of the resistances of the structures. The results can thus be used to guide the preliminary concepts for the electromagnetic characteristics of a tokamak.