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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. T. Hogan, N. A. Uckan
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1504-1508
ITER | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29554
Articles are hosted by Taylor and Francis Online.
The MHD stability limits to the operational space for the International Thermonuclear Experimental Reactor (ITER) have been examined with the PEST ideal stability code. Constraints on ITER operation have been examined for the nominal operating scenarios and for possible design variants. Rather than relying on evaluation of a relatively small number of sample cases, the approach has been to construct an approximation to the overall operational space and to compare this with the observed limits in high-β tokamaks. An extensive database with ∼20,000 stability results has been compiled for use by the ITER design team. Results from these studies show that the design values of the Troyon factor (g ∼ 2.5 for ignition studies and g ∼ 3 for the technology phase), which are based on present experiments, are also expected to be attainable for ITER conditions, for which the configuration and wall-stabilization environment differ from those in present experiments. Strongly peaked pressure profiles lead to degraded high-β performance. Values of g ∼ 4 are found for higher safety factor (qψ ≥ 4) than that of the present design (qψ ∼ 3). Profiles with q(0) < 1 are shown to give g ∼ 2.5, if the current density profile provides optimum shear. The overall operational spaces are presented for g-qψ, qψ-li, q-αp, and li-qψ.