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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.
Masafumi Nakatsuka
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 426-433
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34863
Articles are hosted by Taylor and Francis Online.
Embrittlement of Zircaloy fuel cladding tubes by corrosion media was studied from the viewpoint of its applicability to spent-fuel reprocessing. The results from irradiated as well as unirradiated tubes are summarized as follows: 1.When iodine was employed as the solute, the use of methanol as the solvent caused significant embrittlement of the Zircaloy. 2.For the iodine-methanol solution, the embrittlement increased with the iodine content but saturated at 1 wt%. 3.A water content of up to 10 vol% in the iodine-methanol solution did not decrease the extent of embrittlement. 4.Fracture was of the grain-boundary type, and a fuel cladding tube irradiated to ∼35 GWd/t showed the same embrittlement behavior as an unirradiated one.