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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
J. P. Qian, X. Liu
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1819-1822
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29608
Articles are hosted by Taylor and Francis Online.
Gibbsian segregation has been observed in trinary alloy Al-Li-Mg. The experiment was carried out by means of secondary ion mass spectroscope (SIMS). The experimental results indicated that the lithium concentration on specimen surface reached approximately 100% in the specimen temperature region of 150 to 300 C. The depth profile of Li showed that there was some broadening resulting from recoil implantation by high energy Ar+ ion bombardment. When the specimen temperature exceeded the temperature range in which the lithium enrichment reached the maximum value, beryllium, impurity element in the alloy, segregated to the surface and competed with lithium. Irradiation-induced segregation for Be was also observed in the experiment.
