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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.
S. J. Piet, M. S. Kazimi, L. M. Lidsky
Fusion Science and Technology | Volume 5 | Number 3 | May 1984 | Pages 382-392
Technical Paper | Safety/Environmental Aspects | doi.org/10.13182/FST84-A23113
Articles are hosted by Taylor and Francis Online.
Seven potential safety concerns for deuteriumtritium fusion reactors were examined and the influence of blanket material choice determined. This influence was quantified in terms of relative consequence indices (RCIs) according to prescribed consequence criteria. Selected combinations of structural material (Type 316 stainless steel, HT-9, vanadium alloy, or TZM), primary coolant (pressurized water, helium, lithium, or flibe), and tritium breeder (LiAlO2, lithium, or Li17Pb83) were examined. The analyses and indices were structured to focus on the specific material properties that influence the results, which allows for comparison of materials not included in the present study. The safety concerns that were found to be relatively insensitive (differing by less than an order of magnitude) to material choice are the rate of temperature increase from continued plasma heating following loss of coolant and electromagnetic effects of plasma disruptions. The range of the RCIs was about an order of magnitude for problems concerning after-heat removal, corrosion, and the thermal effects of disruptions. The following problems were found to range in severity over several orders of magnitude according to material choice: potential public health effects from radioactivity release, rapid structural oxidation, blanket chemical combustion, and coolant pressurization.
