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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.
Hai-Di Liu, Fu-Zhi Li, Xuan Zhao, Gui-Chun Yun
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 200-208
Technical Paper | Decontamination/decommissioning | doi.org/10.13182/NT09-A4086
Articles are hosted by Taylor and Francis Online.
We developed a new method for the preparing of a potassium cobalt hexacyanoferrate (PCH)/SiO2 composite as a granulated inorganic adsorbent to remove Cs+ from the radioactive waste solution. The process comprised two steps: The first step was preparing nanoscaled PCH particles, and the second step was stabilizing the PCH particles into the in situ-generated porous silica with aqueous silica sol used as SiO2 source. Granulated composite particles with good rigidity could be successfully prepared with this method. At the same time, the PCH content in the composite could reach 70 wt%, which is one of the highest PCH loads that have been reported.The PCH particles and composite were analyzed with X-ray diffraction, transmission electron microscopy, scanning electron microscopy, energy-dispersive analysis of X-rays, and Brunauer-Emmett-Teller methods. It was indicated by the results that the PCH particles and porous silica were mixed with each other homogeneously in the composite. Adsorption behaviors of the composite upon Cs+ under competition of coexisting ions (H+, Na+, and K+) were studied in batch experiments to determine the distribution coefficient (Kd). The as-fabricated composite exhibited high Cs adsorbing capacity (0.335 meq Cs/g composite) and good Cs+ selectivity from the mixture of competing ions (H+, Na+, and K+). All these characteristics made it a promising material for treating radioactive wastewater.