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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.
André L. Rogister
Fusion Science and Technology | Volume 37 | Number 2 | March 2000 | Pages 271-286
Instabilities and Transport | doi.org/10.13182/FST00-A11963222
Articles are hosted by Taylor and Francis Online.
The phenomenology of transport in magnetically confined plasmas is briefly described and the basic physical concepts underlying the theories of both anomalous and neoclassical transport are reviewed. Anomalous transport is a consequence of supra-thermal electric and magnetic fluctuations driven unstable by various mechanisms. The excited modes saturate by inducing a relaxation of the profiles towards the marginally stable state and via nonlinear coupling of the various modes. Specific theoretical models are described, together with their successes and drawbacks in the light of observed characteristics of plasma confinement. An estimate of the nuclear heating power required to balance the anomalous losses in the International Tokamak Experimental Reactor (ITER) is obtained on the basis of the electrostatic drift wave instability model. Large-scale gyrokinetic turbulence simulations and various “theoretical” transport models are discussed. Recent improvements of neoclassical theory, required in the vicinity of transport barriers, are described.
