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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.
Jason Wilson, James Klein, Kirk Shanahan, Paul Korinko, Anita Poore
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 666-670
Technical Note | doi.org/10.1080/15361055.2017.1290943
Articles are hosted by Taylor and Francis Online.
In facilities containing tritium, all process equipment is contained in inerted gloveboxes operating at slightly negative pressure relative to the process rooms. The gloveboxes have recirculation systems which include a stripper system. The glovebox stripper systems capture tritium from the glovebox atmosphere to minimize facility emissions with the possibility of recovering the tritium.
Hydrogen isotopes released into the gloveboxes are converted to oxide form and removed from the glovebox atmosphere by the glovebox stripper systems – the intended function of these systems. Protiated water (and oxygen) enters the glovebox system in various ways. All water in the gloveboxes is ultimately removed by the stripper system molecular sieve beds which are then processed or disposed of as waste. The water and oxygen enter the glovebox in locations both internal and external to the gloveboxes. The majority of oxygen and water originates external to the gloveboxes in current facility operations.
This study evaluated approaches for water source reduction i.e. reducing the amount of water entering the gloveboxes. The second approach explored options to segregate or prevent the mixing of protiated water in the glovebox with the tritiated water formed as part of the tritium oxidation and capture process used to reduce facility emissions.