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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.
P. K. Mohapatra, P. K. Verma, D. R. Prabhu, D. R. Raut
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1119-1125
Regular Technical Paper | doi.org/10.1080/00295450.2019.1575126
Articles are hosted by Taylor and Francis Online.
Extraction of 137Cs from 1.6 L of diluted aqueous simulated high-level waste (SHLW) (at 1 M HNO3) was carried out using a two-stage centrifugal contactor system (bowl volume 200 mL) into 2 × 10−3 M solution of calix[4]arene-bis-1,2-benzo-crown-6 in phenyltrifluoromethyl sulphone. Batch extraction studies were done to optimize the conditions for the centrifugal contactor runs. Extraction and stripping experiments were carried out at 2000 rotations per minute, keeping the organic and aqueous flow rate at 15 mL/min. Alamine 336 was used at a very low concentration (0.4 vol %) to effect efficient stripping of the extracted radiocesium. The studies were carried out using SHLW as well and the results indicated quantitative extraction and stripping in the first stage of operations while the repeat runs suggested lower extraction as well as stripping efficiencies.
