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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.
L. Bromberg, D. Cohn, J.E.C. Williams, D.L. Jassby, M. Okabayashi
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1013-1018
Next-Generation Devices | doi.org/10.13182/FST83-A22991
Articles are hosted by Taylor and Francis Online.
We describe a design concept for a tokamak that has the capability of sustained ignited operation and utilizes high performance copper plate magnets to minimize size and cost. We refer to this device as LITE for long-pulse ignited test experiment. LITE is designed so that it could be located in the TFTR Test Cell, so that substantial cost savings can be realized. Two design options are considered. Illustrative parameters for the lower beta option (LITE-1) are a major radius of 2.7 m, a maximum magnetic field on axis of 8.1 T, and <β> = 0.05. Steadystate water cooling would be used for nominal DT operation and for very long pulse hydrogen operation. Inertial cooling with liquid nitrogen could be employed for a relatively small number of pulses to provide the highest magnetic fields and ignition margins. The second option (LITE- 2) makes use of a highly shaped plasma to obtain high beta (> 10%) operation. The LITE-2 concept is at a very early stage, so that emphasis in this paper is on the description of LITE-1.
