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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.
Jacob Dobisesky, Joshua Richard, Edward E. Pilat, Mujid S. Kazimi, David M. Carpenter
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 353-377
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-131
Articles are hosted by Taylor and Francis Online.
The primary motivation for using silicon carbide rather than zirconium alloy cladding is its putative improvement in accident resistance, due to slow reactions with water, even at high temperatures. But, fuel management performance will also be an important consideration in its commercial acceptance. Whether backfittable 18- and 24-month cycles can be designed for existing light water reactors, their enrichments, operating characteristics, and fuel costs are questions that the present study undertakes to answer. Also evaluated is the possibility of leveraging silicon carbide's ability to sustain higher fuel duty for increasing power levels and discharge burnups in pressurized water reactors. A preliminary design using fuel rods with the same dimensions as in typical Westinghouse fuel, but with fuel pellets having a 10 vol % central void, has been adopted to mitigate the higher fuel temperatures when silicon carbide is used. This allows design of 18- and 24-month cycles that meet present-day operating constraints on peaking factor, boron concentration, reactivity coefficients, and shutdown margin, while achieving batch average discharge burnups up to 80 MWd/kg U, as well as power uprates of 10% and possibly 20%. Control rod configuration modifications may be required to meet the shutdown margin criterion for the 20% uprate. For nonuprated cores, silicon carbide–clad fuel may have a fuel cost advantage, especially with increasing discharge burnup, provided the fuel manufacturing cost is close to that of Zircaloy tubes. The economics of the fuel cycle also improve with power uprates, as the value of the additional energy generated may substantially exceed the advantage from fuel cost alone.