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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.
Yutaka Matsumoto, Tatsuhiko Nagaura, Tsuguhiro Watanabe, Shun-Ichi Oikawa
Fusion Science and Technology | Volume 39 | Number 1 | January 2001 | Pages 309-315
Poster Presentations | doi.org/10.13182/FST01-A11963468
Articles are hosted by Taylor and Francis Online.
Detailed stracture of the magnetic field in the Large Helical Deveice (LHD) is studied numerically. The connection length of the divertor field line is found to be the order of several km or more. The possibility of the mirror-confined plasma in the chaotic field line region is shown. The divertor plasma model is proposed based on the long connection length and the existence of the mirror-confined plasma in the chaotic field line region. A new ICRF heating scheme (runaway ion heating scheme) for LHD is also proposed based on the existence of the mirror-confined plasma in the core plasma region.
