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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.
Scipione Bobbio, Enzo Coccorese, Giulio Fabricatore, Raffaele Martone, Guglielmo Rubinacci
Fusion Science and Technology | Volume 7 | Number 3 | May 1985 | Pages 345-360
Technical Paper | Plasma Engineering | doi.org/10.13182/FST85-A24555
Articles are hosted by Taylor and Francis Online.
In the international tokamak reactor (INTOR), the problem of the passive control of the vertical instability is to be solved by means of suitably shaped saddle coils to be embedded in the blanket structure. The efficiency of such a system depends on the characteristics of the passive conductors and on the plasma equilibrium as well as on the type of plasma displacement assumed. To cover the physical uncertainties caused by the model assumptions for the plasma with respect to the motion on a slow time scale (of the order of several tens of milliseconds) corresponding to efficient passive stabilization, four different plasma displacement models are considered and compared with each other. A stability analysis is performed using the energy principle, expressed in circuital form. The results of the INTOR analysis are presented and discussed, showing in particular that under very general conditions the optimum stabilization efficiency is obtained for passive conductors situated at ∼60 deg above and below the horizontal midplane at the outboard side. The effect of the geometric parameters of the saddle coils (e.g., area and shape of the cross section, toroidal segmentation, etc.) on the stabilization efficiency is investigated; a parametric study of these dependences is presented. General conclusions applicable to INTOR are drawn.
