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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. K. Heung
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 859-864
Tritium Safety | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30512
Articles are hosted by Taylor and Francis Online.
In the new Replacement Tritium Facility (RTF) at the Savannah River Site, gloveboxes and stripper systems are used to minimize tritium release to the environment. The RTF was built to handle kilogram levels of tritium. It was started up and has been in operation since January 1994. The glovebox-stripper system has performed well in confining tritium leaks from the process. The tritium level in the gloveboxes has been maintained at below 0.1 Ci/m3 under normal conditions. During a large leak of tritium gas from the process to a glovebox, the tritium concentration in the glovebox shot up to about 4000 Ci/m3. However, there was no significant release of tritium to the environment. The tritium reading in the glovebox decreased to a 10 Ci/m3 level after 6 days of stripping. The performance of the glovebox-stripper system during this tritium leak and the possible factors for the long and slow decay of the tritium concentration in the glovebox are discussed in this paper.