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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.
R. L. Boivin, J. L. Luxon, M. E. Austin, N. H. Brooks, K. H. Burrell, E. J. Doyle, M. E. Fenstermacher, D. S. Gray, M. Groth, C.-L. Hsieh, R. J. Jayakumar, G. R. McKee, C. J. Lasnier, A. W. Leonard, R. A. Moyer, T. L. Rhodes, J. C. Rost, D. L. Rudakov, M. J. Schaffer, E. J. Strait, D. M. Thomas, M. Van Zeeland, J. G. Watkins, G. W. Watson, W. P. West, C. P. C. Wong
Fusion Science and Technology | Volume 48 | Number 2 | October 2005 | Pages 834-851
Technical Paper | DIII-D Tokamak | doi.org/10.13182/FST05-A1043
Articles are hosted by Taylor and Francis Online.
The DIII-D tokamak, located at General Atomics in San Diego, California, has long been recognized as being one of the best diagnosed magnetic fusion experiments. Composed of more than 50 individual systems, the diagnostic set takes advantage of a high number of large-aperture access ports. These instruments are used in support of basic control of the tokamak and experiments in the transport, stability, boundary and heating, and current drive science areas. These systems have contributed to the success of the Advanced Tokamak program, in addition to the many contributions to our physics understanding and real-time control of fusion-relevant plasmas. Numerous novel techniques have been developed, tested, and fielded on DIII-D including new approaches required for a burning plasma experiment. Details of the diagnostic systems will be described along with some illustrative recent results.
