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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.
H. Y. Khater, R. R. Peterson, I. N. Sviatoslavsky
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 1013-1017
Safety and Environment | doi.org/10.13182/FST01-A11963375
Articles are hosted by Taylor and Francis Online.
Using xenon as a fill gas in IFE chambers results in generating a large amount of radioactive xenon, iodine, and cesium isotopes. The cesium isotopes, 134Cs and 136Cs, and the iodine isotope, 126I, would produce a high level of off-site dose (62.13 rem) at the plant site boundary if they were released entirely to the environment during an accident. The xenon gas is pumped out of the chamber (recycled) during operation to remove unburned T2 and D2. Removing the Cs and I isotopes from the Xe gas during this recycling process will reduce the Cs and I inventories inside the chamber to negligible values. This process limited the off-site dose caused by the accidental release of Xe from the chamber of the SOMBRERO power plant to 29.9 mrem, which is less than the 1 rem no-evacuation limit. Using krypton, argon or neon as fill gases will result in producing lower levels of off-site dose than xenon.