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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.
Akira Oikawa, Naoyuki Miya, Kozo Kodama, Takashi Umehara, Takeshi Yamazaki, Kei Masaki, Isamu Akiyama, Kozo Matsushita, Nobuyuki Hosogane
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 612-616
Device, Facility, and Operation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22661
Articles are hosted by Taylor and Francis Online.
Effluent of tritium in vacuum exhaust in JT-60 through the stack to environment always remains a level below detectable level (<10−5Bq/cm3 at the stack, <10−7Bq/cm3 at the site boundary). Though tritium concentration of drain water is below the limit of regulations of the local agreement and the law, small tritium contamination in the facility drain and in the rain drain of stack appeared occasionally. For a scheduled maintenance work of the in-vessel components, following an annual deuterium plasma discharge campaign, a 4-week no-deuterium (H or He) plasma discharge campaign and the succeeded ventilation by room air allow to reduce tritium on the interior surface of in-vessel components. This cleaning up shots and air introduction allowed workers to enter into the vacuum vessel. Air blow well tends to remove surface tritium elements and would be necessary before disassembly and replacement of components on vacuum pumping lines.