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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.
Fu-Zhi Li, Meng Zhang, Xuan Zhao, Tao Hou, Li-Jun Liu
Nuclear Technology | Volume 172 | Number 1 | October 2010 | Pages 71-76
Technical Paper | Nuclear Plant Operations & Control | doi.org/10.13182/NT10-A10883
Articles are hosted by Taylor and Francis Online.
The rapid development of the nuclear power plant (NPP) in China leads to increasing attention to the minimization of radioactive waste. The primary coolant is one of the sources of low-level radioactive wastewater and must be decontaminated before its discharge to the environment. One of the possibilities is by means of continuous electrodeionization (CEDI) technology. In this paper the lab-scale experiments demonstrate that CEDI can offer favorable decontamination of primary coolant in NPP, with minimized radioactive spent resin production. Displacement of the anion exchanger by weak base anion exchangers in a CEDI module can improve the Co2+ and Sr2+ removal. In the dilute effluent of the modified module, Co2+ and Sr2+ concentrations are below 2 ngl-1 and 58 to 114 ngl-1 , respectively, which is much lower than the commercial one of 205 to 289 ngl-1 and 268 to 326 ngl-1 . This displacement has a negligible influence on the electrical resistance of the module.
