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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. Bucalossi, on behalf of Tore Supra Team
Fusion Science and Technology | Volume 56 | Number 3 | October 2009 | Pages 1366-1380
Technical Papers | Tore Supra Special Issue | doi.org/10.13182/FST09-A9183
Articles are hosted by Taylor and Francis Online.
One of the main missions of the Tore Supra tokamak was to open the route toward long-pulse plasma discharges in order to investigate phenomena that are involved in steady-state plasma control. In 1992, a 1-min flattop 1-MA discharge was performed with 2.5 MW of lower hybrid current drive (LHCD) power, the main limitation being the available flux. In 1996, at 0.8 MA, the duration was extended to 120 s (290 MJ injected energy), limited by in-vessel uncontrolled outgassing of inertial parts (away from the last closed flux surface) slowly heated by the plasma radiation. At the same time, fully noninductive operation was sustained at 0.6 MA for more than 1 min using two feedback loops: the control of the loop voltage (kept at zero) with the primary and the control of the plasma current with the LHCD power.Following these results, a major upgrade of the plasma-facing components was undertaken (Composants Internes et Limiteur project) and fully implemented in 2002. The vacuum vessel is now practically fully covered with actively cooled plasma-facing components monitored by a set of infrared endoscopes. In 2003, 1 GJ of injected/extracted energy was achieved in a 6-min, 0.5-MA discharge. All the plasma parameters were kept constant during the whole discharge, the plasma current being fully noninductively driven by 3 MW of LHCD. The pulse length limitation came from the aging klystron, originally designed for 30-s operation.Experimental results and analysis of the physics involved in these long-pulse discharges are reported and discussed.