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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.
A. Moisseytsev, Y. Tang, S. Majumdar, C. Grandy, K. Natesan
Nuclear Technology | Volume 175 | Number 2 | August 2011 | Pages 468-479
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT11-A12318
Articles are hosted by Taylor and Francis Online.
To improve the economic characteristics of fast reactors, researchers are developing advanced structural materials for application to reactor components. These advanced materials provide higher strength at elevated temperatures. Coupled thermal-hydraulic and structural analyses have been carried out to investigate the benefits of the advanced structural materials for a specific fast reactor design: the Advanced Burner Reactor (ABR) developed at Argonne National Laboratory. The benefits of the advanced materials, in terms of increased design margins, possible longer lifetime, thinner structures, and higher operating temperatures, were calculated for the major ABR structural components, including the reactor vessel, the core support structure, the intermediate heat exchanger, the intermediate heat transport system piping, and the steam generator. For each structure, the possible reduction in the component thickness was calculated and was converted into estimates of the commodities savings provided by the use of the advanced materials. Overall, a significant material mass saving of [approximately]40% was calculated for the considered fast reactor structures.