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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.-L. Duchateau, M. Coatanea, B. Lacroix, S. Nicollet, D. Ciazynski, P. Bayetti
Fusion Science and Technology | Volume 64 | Number 4 | November 2013 | Pages 705-710
Technical Paper | doi.org/10.13182/FST13-A24089
Articles are hosted by Taylor and Francis Online.
The quench of one of the ITER magnet systems is an irreversible transition of the conductor from superconducting to normal resistive state. The normal zone propagates along the cable-in-conduit conductor, dissipating a large power. The detection has to be fast enough (1 to 2 s) to initiate the dumping of the magnetic energy and avoid irreversible damage of the systems.The experience of CEA is based on the operation of the superconducting tokamak Tore Supra for more than 20 years. In support of ITER, CEA was also very involved in quench detection investigations during these past 3 years.The primary quench detection in ITER is based on voltage detection, the most rapid detection. The very magnetically disturbed environment during a plasma scenario makes the voltage detection particularly difficult, inducing large inductive components across the pulsed coils (10 kV) or coil subcomponents. Voltage compensations therefore have to be designed to discriminate the resistive voltage associated with the quench.A secondary detection based on a thermohydraulic signals system also has to be investigated to protect the environment in case of a nondetected quench, especially for the largest ITER system, which is the toroidal field system with a stored energy of 40 GJ.