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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.
Marco Cigarini, Mario Dalle Donne
Nuclear Technology | Volume 80 | Number 1 | January 1988 | Pages 107-132
Technical Paper | Advanced Light Water Reactor / Fission Reactor | doi.org/10.13182/NT88-A35553
Articles are hosted by Taylor and Francis Online.
A parametric thermohydraulic study for an advanced pressurized water reactor (APWR) with a tight fuel rod lattice has been performed. The APWR improves uranium utilization. It has been assumed that the APWR core should be placed in a modern German pressurized water reactor (PWR) plant. Within this study ∼200 different reactors have been calculated. The tightening of the fuel rod lattice implies a decrease of the net electrical output of the plant. APWR cores mean higher core pressure drops and higher water velocities in the core region. The cores tend to be shorter and the number of fuel rods higher than for the PWR. In the range of interest, homogeneous and heterogeneous reactors are about equivalent (same net electrical output of the plant for the same ratio between water and fuel rod volume). For homogeneous reactors the optimum designs are for H/d = 20 (H= axial pitch of the integral spiral ribs on fuel rod surface, d = diameter of the fuel rod) and for heterogeneous reactors for H/d = 35.