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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.
Werner Faubel, Sameh A. Ali
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 60-65
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34282
Articles are hosted by Taylor and Francis Online.
The technical feasibility of partitioning concentrated nitric acid intermediate-level waste (ILWC) solutions from the Purex process into a small volume of high-level waste and a large volume of low-level waste using sorption methods is demonstrated for 1-ℓ batches. Cesium-134 and 137Cs are selectively separated with a decontamination factor (DF) greater than 1 × 105 in a newly developed “suspended-bed” column filled with the microporous inorganic exchanger ammonium molybdophosphate. The 125Sb and the actinides and lanthanides with a 3+ valence state are retained with DFs between 40 and 1000 on metal oxides of antimony and manganese and on an extraction column containing n-octyl(phenyl) N,N-diisobutyl carbamoyl methyl phosphine oxide, respectively. Ruthenium-106 and 60Co are removed in a column loaded with dimethyl glyoxime and have DFs greater than 20. The amount of secondary wastes arising from absorber materials is calculated to be 300 kg for a 350 t/yr reprocessing plant with an ILWC volume of ∼0.5 m3/t of heavy metal.